Programme
and
Abstracts
Organized by the:
International Conference on
Applications of
Radiation Science
and Technology
24–28 April, 2017
Vienna, Austria
Programme & Book of Abstracts
Version: July 7, 2017, web enabled
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Colophon
This book has been assembled from the abstract sources submitted by the con-
tributing authors via the Indico conference management platform. Layout, editing,
and typesetting of the book, including customized TEX & LATEX macros, was done
by Dr. P. Knowles, LogrusData, Vienna, Austria. The font is TeX Gyre Pagella, a
decendent of Hermann Zapf’s Palatino.
This book is PDF hyperlinked: activating coloured text will, in general, move you
throughout the book, or link to external resources on the web.
CN–249 Intl. Conf. Appl. of Rad. Sci. &Tech. ICARST–2017
Introduction
The saga of the radiation sciences goes back to the astonishing discoveries by Rönt-
gen and the Curies at the turn of the twentieth century. Driven initially by the
quest to comprehend the complex effects of radiation fields on chemical processes,
radiation chemistry, in particular, has emerged as a valuable tool for understanding
the intricate chemical reactions of importance to a variety of disciplines. It has also
found wide-ranging commercial applications in such areas as materials processing,
health care, food and agriculture. While the development of ultrafast techniques
such as pulse radiolysis has allowed for the exploration of important chemical
processes, the simultaneous technological development of high intensity gamma
radiation sources and high powered electron beam accelerators has assured the ra-
diation sciences’ ongoing tryst with industry, leading to the successful commercial
utilization of many of the applications developed by scientists and researchers. The
International Atomic Energy Agency (IAEA), working in close partnership with
its Member States as well as with professional scientific bodies and the industry,
has striven to maximize the contribution of radiation sciences and technologies
towards the achievement of the Member States’ development priorities in a safe
manner.
While acknowledging the many innovations and accomplishments achieved in the
field of radiation sciences so far, it is now time to take a comprehensive look at
their status in academia and industry in the years ahead and their ability to meet
the challenges of contemporary times. Radiation scientists are currently engaged
in addressing issues related to producing advanced high performance materials
through “green” industrial processes ensuring cleaner environment, attaining a
thorough understanding of the chemical effects of radiation under extreme con-
ditions (which is important for extending the lifetime of present nuclear reactors,
making their fuel cycles safer and secure to operate), and overcoming impedi-
ments regarding the transportation and storage of waste materials (which requires
novel approaches to address the complicated chemistry at interfaces). Radiation
technologists on the other hand are faced with such tremendous challenges as
ensuring the safe and reliable operation of large radiation facilities, implementing
requisite international standards for process control, ensuring the continued sup-
ply and transport of large 60Co consignments across continents, and developing a
new generation of high power electron beam accelerators and X-ray sources for
emerging applications. Besides radiation processing applications, there are other
radiation technologies such as the use of radiotracers to improve and optimize the
performance of industrial processes, as well as to study environmental processes,
and the use of nucleonic measurement systems to control the quality of products.
1
ICARST–2017 Intl. Conf. Appl. of Rad. Sci. &Tech.
Scientific Committee
Namez Country/International Organization
External Members:
Abraham Adu Gyamfi Ghana
Mohamad Al Shaikhly USA
Saphwan Al-Assaf United Kingdom
Muthanna Al-Dahhan USA
Jefferson Vianna Bandeira Brazil
Haifa Ben Abdelouahed Tunisia
Tor Bjørnstad Norway
Jean-Louis Boutaine France
Aleksandr Bryazgin Russia
Jamal Chaouki Canada
Xavier Coqueret France
Nick Cutmore Australia
Clelia Dispenza Italy
Ferenc Ditroi Hungary
Joachim Gehring Germany
Sara Goldstein Israel
Mariano Grasselli Argentina
Paul Gray Canada
Olgun Guven Turkey
John Havermans Netherlands
Celina Horak Argentina
Catherine Hughes Australia
Iqbal Hussain Khan Pakistan
Joon-Ha Jin Korea, Republic of
Sung-Hee Jung Korea, Republic of
András Kovács Hungary
Florent Kuntz France
Paul Livolsi France
Ademar Lugao Brazil
zNames are listed alphabetically in each section.
2
Intl. Conf. Appl. of Rad. Sci. &Tech. ICARST–2017
Namez Country/International Organization
Yasunari Maekawa Japan
Arne Miller Denmark
Josef Mittendorfer Austria
Ioan Valentin Moise Romania
Mehran Mostafavi France
Young-Chang Nho Korea, Republic of
Wei Peng China
Harish Jagat Pant India
Bernard Ponsard Belgium
Olivier Potier France
Indira Prityadarsini India
Pablo Vasquez Salvador Brazil
Maria Helena Sampa Brazil
Thierry Sauvage France
Zdislaw Stegowski Poland
Yongxia Sun Poland
Erzsebet Takács Hungary
Jovan Thereska Albania
Varinder Tikku India
Piotr Ulanski Poland
Jianlong Wang China
Laszlo Wojnárovits Hungary
Guozhong Wu China
Maolin Zhai China
Israel Zilbermann Israel
Zbigniew Zimek Poland
Internal Members:
Patrick Brisset IAEA
Bum Soo Han IAEA
Sunil Sabharwal IAEA
Agnes Safrany IAEA
zNames are listed alphabetically in each section.
3
ICARST–2017 Intl. Conf. Appl. of Rad. Sci. &Tech.
Steering Committee
Namez Country/International Organization
Rachad Alami Morocco
Wilson A. P. Calvo Brazil
Andrzej G. Chmielewski Poland
Marie-Claude Dubois-Clochard France
Ema Castro Gamero Peru
El-Sayed Hegazy Egypt
Monique Lacroix Canada
Jean Pierre Leclerc France
Shen Lixin China
Lydia Paredes Mexico
Suresh Pillai USA
Quang Nguyen Huu Viet Nam
Natesan Ramamoorthy India
Masao Tamada Japan
Seungho Yu Republic of Korea
zNames are listed alphabetically in each section.
4
Intl. Conf. Appl. of Rad. Sci. &Tech. ICARST–2017
IAEA Conference Secretariat:
Radioisotope Products and Radiation Technology Section
International Atomic Energy Agency
Vienna International Centre, PO Box 100
1400 Vienna, Austria
icarst2017@iaea.org
Scientific Secretary:
Mr João Alberto Osso Júnior
tel: +43 1 2600 21748
icarst2017@iaea.org
Local Administration Support:
Team Assistants Enrique Nacif
Robby Rizaldi
Adrene Despars
Administrative Assistant Kristina Pleskach
Interns Tihomir Bonev
Jaidev Dhavle
Consultant Aleksandra Peeva
Ana Regina Marquez Lacayo
Voluntary Contribution Co-ordination Veronika Komaromi
Leyla Abdulhalim Al-Gad
Marieta Samac
Conference Clerks Karen Avanesyan
Jacob Frischknecht
Minja Jovanovic
Karl Krizek
Liubov Kulaeva
Conference Services:
Division of Conference and Document Services (MTCD)
International Atomic Energy Agency
Vienna International Centre, PO Box 100
1400 Vienna, Austria
Conference Coordination:
Ms Julie Zellinger
tel: +43 1 2600 21321
J.Zellinger@iaea.org
5
ICARST–2017 Intl. Conf. Appl. of Rad. Sci. &Tech.
Exhibition coordination:
Ms Viktorija Joranovska
tel: +43 1 2600 21490
V.Jordanovska@iaea.org
Exhibits
Exhibits will be located in M–Building, on floors M0E and M01, and the Rotunda.
Participants are encouraged to view the exhibits during the hosted coffee breaks.
The following organizations and companies will have information stands during
the conference.
– CGN Dasheng Electron Accelerator Technology Co. Ltd.
– National Association for Advancement of Radioisotopes and Radiation in
Industry (NAARRI)
– China Isotope & Radiation Corporation (CIRC)
– IBA Industrial
– World Council on Isotopes (WCI)
– Baltic Scientific Instruments (BSI)
– EB Tech Co. Ltd.
– Gamma Service Group
– International Source of Suppliers and Producers Association (ISSPA)
– Nuctech Co. Ltd.
– Canberra Packard Central Europe GmbH
– Flir Systems, GmbH
– Institute of Isotopes Co. Ltd. (IZOTOP)
– Shimadzu HandelsgesmbH
–Wuxi EL PONT Radiation Technology Co. Ltd.
– Aérial
– Atomtex
– JSC Isotope
– Meet Instruments GmbH
–Mirion Technologies
– SI Detection
– Sterigenics
– Steris AST
– UAB Polimaster Europe
– Vanform Corporation
6
Intl. Conf. Appl. of Rad. Sci. &Tech. ICARST–2017
Exhibits (continued)
– CEA-INSTN
– VWR International GmbH
– Dozimetrs Ltd.
– Berthold Technologies GmbH
– Best Theratronics
– Budker Institute of Nuclear Physics
– F&J Speciality Products
– Harwell Dosimeters Ltd.
– Beijing SanQiangHeLi Radiation Engineering Technology (SQHL)
– Elysia-Raytest GmbH
– Fraunhofer FEP
– Gamma Technical Corperation
– GC Technology GmbH
– Institute of Nuclear Chemistry and Technology (INCT)
– International Irradiation Association (IIA)
– Nordion
– Pacific Northwest National Laboratory (PNNL)
– Texas A&M AgriLife Research
–World Nuclear Association/World Nuclear University
– ZRF RITEC SIA
Representatives fromMEVEX and Comissão Nacional De Energia Nuclear (CNEN-
IPEN) will also be at ICARST.
The fact that the IAEA has provided facilities for exhibiting equipment and prod-
ucts at the conference does not imply that it endorses the equipment and products.
7
ICARST–2017 Intl. Conf. Appl. of Rad. Sci. &Tech.
Working Language & Resolutions
Working Language: English. No simultaneous interpretation will be provided.
Resolutions: No resolutions may be submitted for consideration on any
subject; no votes will be taken.
Conference Location
International Atomic Energy Agency (IAEA)
Wagramer Str. 5, 1220 Vienna, Austria
M–Building Conference Rooms: M01 (First Floor) Board Room B/M1
RoomM2
G
Vienna International Center
(VIC) Cafeteria
F
M-Building
ICARST RotundaA C Bank, Post Office
Conference (1st floor)
B Fountain D E
U1 U-Bahn Station
“Kaisermühlen–VIC” Registration
(Gate 1, Sunday Apr. 23)
(15:00–18:00) Hotel NH
City Centre Security Screening Danube City
Wagramer Straße
Hotel Hotel
Kaiserwasser Park Inn
Wireless Internet
Public access WiFi is available throughout the IAEA buildings. Select access point
wlan-guest and the connection will be automatic: there is no password.
8
nstein Str
aße
Leonard–
Ber
Intl. Conf. Appl. of Rad. Sci. &Tech. ICARST–2017
Hosted Coffee Breaks
Therewill be complimentarymid-morning and afternoon refreshmentswhich have
been fundedusing the voluntary contributions from those exhibitors acknowledged
in the last few pages. Participants are encouraged during these breaks to not
only enjoy the refreshments but to profit from the posters and exhibition stands
displayed on M–Building floors M0E andM01, and in the C–Building ground floor
Rotunda.
Refreshments, snacks and lunch can be purchased either from the VIC Cafeteria
and Restaurant on the ground floor of the F–building, or from the coffee corners
located on the M–Building ground floor or 7th floor of the C–Building.
Conference Proceedings
The Conference Proceedings containing selected original contributions will be
published as a special issue of Nukleonika, an open access journal with special
rates for ICARST. The best 30 peer-reviewed manuscripts will be selected for
publication according to the journal’s criteria.
Participants are encouraged to submit their contribution together with the state-
ment of originality of the work in electronic format to the Guest Editor, Mr Natesan
Ramamoorthy, (nramasta@gmail.com). The submission deadline is April 14th 2017.
Instructions for manuscript preparation can be found on the ICARST website.
Posters
All posters will be displayed for the full duration of the conference on the ground
floor of the M–Building and in the A–Building concourse. Authors are asked to be
available at their posters for discussions with interested participants according to
their assigned poster session (Wednesday or Thursday, 14:15–16:15). Participants
are also encouraged to view the posters during the hosted coffee breaks.
Book of Abstracts
This book contains all contributions and abstracts to be presented at the conference.
Abstracts have been edited for IAEA style uniformity. The views expressed remain
the responsibility of the named authors. No responsibility is held by the organizers
for any material reproduced, or linked, in this book.
9
ICARST–2017 Intl. Conf. Appl. of Rad. Sci. &Tech.
Abbreviations
AAEA Arab Atomic Energy Agency
CFD Computational Fluid Dynamics
CL Closing Session
E&T Education and Training
EB Electron Beam
EC European Commission
ENEN European Nuclear Education Network
EU European Union
IAEA International Atomic Energy Agency
ISTRA International Society of Tracers and Radiation Applications
KAERI Korea Atomic Energy Research Institute
NAA Neutron Activation Analysis
OECD Organisation for Economic Co-operation and Development
OECD/NEA Organisation for Economic Co-operation and
Development/Nuclear Energy Agency
OP Opening Session
RPT Radioactive Particle Tracking
TSec Technical Secretary
10
M–Building, M0E (Ground Floor) ICARST–2017
11
Snack Bar
M0E68
Cloak Room Briefing
M0E67
Office
Up
Registration
& M1 —Posters—
Information
A–Building M1: CGN Dasheng Electron Accelerator Technology Co. Ltd.
&
Rotunda
ICARST–2017 A–Building, VIC
A–Elevators
12
NB: Some posters are on
display in the M–Building
on the ground floor
ing
uild–B —M ste
rs
Po —— Poste
— Fountain —
rs
P —
oste
rs & oMain Entrance sters CP — –B— R
u
o ilt du in nd ga
C–Building, Rotunda ICARST–2017
  
C1
C2 C6
C3 C5
C4
To A–Building
To M–Building
C22
C23 C
21
24 C20C
C19
13
C1: Aérial
C2: Mirion Technologies & CANBERRA
PACKARD Central Europe GmbH
C3: UAB Polimaster
C4: Atomtex & Meet Instruments GmbH
C5: Baltic Scientific Instruments (BSI)
C6: Texas A&M Agrilife
C7: Berthold Technologies GmbH
C8: Nordion
C9: SI Detection
C10: Pacific Northwest National
To Laboratory (PNNL)Cafete C11: Fraunhofer FEPria C12: Elysia-raytest GmbH
C13: ZRF RITEC SIA
C14: International Irradiation Association
(IIA)
C18 C17 C16 C25 C26 C27 C15: World Nuclear Association/World
C13 C14 C15 C30 C29 C28 Nuclear University
C16: Shimadzu HandelsgesmbH
C17: Vanform Corporation
C18: STERIS AST
C19: JSC Isotope
C20: Wuxi EL PONT Radiation
Technology Co. Ltd.
C21: Nuctech Co. Ltd.
C22: Beijing SanQiangHeLi Radiation
Engineering Technology (SQHL)
C23: STERIGENICS
C24: Harwell Dosimeters Ltd.
C25: Best Theratronics
C26: F&J Specialty Products Inc.
C27: Budker Institute of Nuclear Physics
C28: CEA-INSTN
C29: VWR International GmbH
C30: Dozimetrs Ltd.
  
 
C12
C7 C11
C8 C10
C9
  
Fo
M ua ni & tn a iE nntrance
ICARST–2017 M–Building, M01 (First Floor)
M3: EB Tech Co. Ltd. M11: Gamma Service Group
M4: ISSPA M12: GC Technology GmbH
M5: IBA Industrials M13: Inst. Nucl. Chem. & Tech. (INCT)
M6-7: NAARRI M14: Gamma Technical Corporation
M8: China Isotope & Radiation Corp. (CIRC) M15: Flir Systems GmbH
M9: World Council on Isotopes M16: Institute of Isotopes Co. Ltd. (IZOTOP)
M10: International Atomic Energy Agency
M16 M15 M14 M13 M12 M11 Coffee
Exhibits
14
Board Room B/M1
Room M2
Up Exhibits
M3 M4 M5 M6-7 M8 M9 M10
Timetable ICARST–2017
15
Day Monday Tuesday Wednesday Thursday Friday
Date Apr. 24, 2017 Apr. 25, 2017 Apr. 26, 2017 Apr. 27, 2017 Apr. 28, 2017
08:00 Registration Parallel Sessions Parallel Sessions Parallel Sessions Parallel Sessions
09—:00 10:00 Opening A04 B04 A08 B08 A11 B11 A14 B15
11:00 OP
Coffee break, Posters and Exhibits
11:15 Parallel Sessions Parallel Sessions Parallel Sessions Parallel Sessions Parallel Sessions
— A01 B01 A05 B05 A09 B09 A12 B12 A15 B16
13:15
Lunch break: 13:15–14:15
14:15 Parallel Sessions Parallel Sessions Poster Sessions Parallel Sessions 14:15 Closing
—
16:15 A02 B02 A06 B06 PA1 PB PA2 B13 CL
Coffee break, Posters and Exhibits
16:30 Parallel Sessions Parallel Sessions Parallel Sessions Parallel Sessions
—
18:30 A03 B03 A07 B07 A10 B10 A13 B14
18:30 Welcome S01 S02
—
20:00 Reception Chinese Mission ISTRA
Side Event Side Event
ICARST–2017 Monday 24 April 2017
REG 08:00–16:00 Conference Registration
Venue: Entrance M–Building
OP 10:00–11:00 Opening Plenary
Venue: Board Room B/M1
Time Id Presenter
10:00 OP-01 Y.Amano IAEA Opening Remarks
10:10 OP-02 A.Malavasi IAEA Welcome by DDG-NA
10:20 OP-03 D. Yang IAEA Welcome by DDG-TC
10:30 OP-04 A. G.Chmielewski Poland Ionizing Radiation: Innovative and
Effective Tool for Science and Industry
Coffee break: 11:00–11:15
A01 11:15–13:15 Trends in Radiation Science and
Venue: Board Room B/M1 Technology
Chair: Natesan Ramamoorthy (India)
TSec: João Alberto Osso Júnior (IAEA)
Time Id Presenter
11:15 A01-01 P.Ulański Poland Radiation Synthesis of Polymer Nanogels
for Biomedical Applications
11:35 A01-02 L. Shen China, P. R. Status and Prospect of Application of
Radiation Science and Technology in
China: A National Report
11:55 A01-03 B. Croonenborghs USA Emerging Areas of Radiation Sterilization
12:15 A01-04 L. V.Abad Philippines Radiation-Modified Carrageenan as Plant
Food Supplement: Making a
Breakthrough with Philippine Farmers
12:35 A01-05 J.Wishart USA Recent Progress in Pulse Radiolysis
Detection Methods and their Application
to Ionic Liquid-Based Systems for Closing
the Nuclear Fuel Cycle
12:55 A01-06 P.Vasquez Brazil Overview of Disinfection of Cultural
Heritage Artefacts and Archive Materials
by Ionizing Radiation in Brazil: Culture
Meets Nuclear
Lunch break: 13:15–14:15
16
Mon
Monday 24 April 2017 ICARST–2017
B01 11:15–13:15 Advances and Trends in Radiotracer and
Venue: Room M2 Radiation Science and Technology I
Chair: Tor Bjørnstad (Norway)
TSec: Patrick Brisset (IAEA)
Time Id Presenter
11:15 B01-01 Q.Nguyen Huu Viet Nam Improved Procedures for Preparation of
Argon-41 Gaseous Radiotracer from Solid
Clathrate Compound
11:35 B01-02 L.Kalo India Experimental Study of Conical Fluidized
Bed Using Radioisotope Based Technique
11:55 B01-03 J. Phirani India Predicting Dead Pore-Volume of Pores in a
Porous Media from Single Tracer
Experiment
12:15 B01-04 S. Roy India Application of RPT and Densitometry for
Measuring Liquid Velocity Field and Void
Fraction in Convective Boiling Flows
12:35 B01-05 C. H. de Mesquita Brazil Holdup Analysis of a Bubble Column
Using an Industrial Fourth Generation
Like γ-Ray Tomography
—Discussion—
Lunch break: 13:15–14:15
A02 14:15–16:15 Advanced Polymeric Materials
Venue: Board Room B/M1
Chair: Celina Horak (Argentina)
TSec: Agnes Safrany (IAEA)
Time Id Presenter
14:15 A02-01 O.Güven Turkey Past, Present and Near Future of
Radiation Processing of Polymers
14:35 A02-02 X.Coqueret France Radiation Curing by Cross-Linking
Polymerization of Multifunctional
Monomers: A Comparison Between Free
Radical and Cationic Mechanisms
14:55 A02-03 M. Lacroix Canada Use of Irradiation, for the Development of
Active Edible Coatings, Beads and
Packaging to Assure Food Safety and to
Prolong Preservation
15:15 A02-04 Z.Ghazali Malaysia Radiation Grafted Antimicrobial Film for
Advanced Active Packaging Application
Continued. . .
17
Mon
ICARST–2017 Monday 24 April 2017
A02 continued. . .
Time Id Presenter
15:35 A02-05 C.Vasile Romania Radiation Mediated Bioactive
Compounds Immobilization on Polymers
to Obtain Multifunctional Food Packaging
Materials
15:55 A02-06 E.Hegazy Egypt Radiation Processing of Natural and
Synthetic Polymers for Potential
Applications
Coffee break: 16:15–16:30
B02 14:15–16:15 Education, Training and Safety
Venue: Room M2
Chair: Thorsten B. O. Jentsch (Germany)
TSec: Patrick Brisset (IAEA)
Time Id Presenter
14:15 B02-01 O. Potier France A New Approach to Teach Beginners How
to Analyze Tracing Results by a Rapid
Visual Method
14:35 B02-02 P. Livolsi France Education Training: INSTN Designated as
an IAEA Collaborating Centre
14:55 B02-03 P. Brisset IAEA Training and Certification in Radiotracers
and Sealed Sources Industrial
Applications
15:15 B02-04 D. Telleria IAEA The IAEA Methodology for Radiological
Protection of the Environment, Including
Human and Non-Human Biota
15:35 B02-05 A.Mahjoub Tunisia Radiation Sciences and Applications
Programme in Arab Countries
15:55 B02-06 S. A.Masinza Kenya Quality Management in Radiotracer
Technology and Sealed Source
Applications
Coffee break: 16:15–16:30
18
Mon
Monday 24 April 2017 ICARST–2017
A03 16:30–18:30 Advances and Trends in Radiation
Venue: Board Room B/M1 Science and Technology
Chair: Xavier Coqueret (France)
TSec: Agnes Safrany (IAEA)
Time Id Presenter
16:30 A03-01 M.Zhai China, P. R. Novel Ion Exchange Membranes
Synthesized by Radiation Grafting
Technique for Application in Vanadium
Redox Batteries
16:50 A03-02 J. Li China, P. R. Irradiation Induced Modification of
Nanoporous Metal Organic Frameworks
17:10 A03-03 G. Burillo Mexico Synthesis of Amine-Containing Surfaces
in Poly(Tetrafluoroethylene) by
γ-Radiation
17:30 A03-04 Y.Kodama Brazil Polycarbonate Chromatography Column
to Be Used in a 99Mo/99mTc Generator
Irradiated in Saline Solution with EB and
γ-Rays
17:45 A03-05 G.Melilli France EB Irradiation on Piezo-PVDF: Beneficial
Effect for Harvesting Energy Application
18:00 A03-06 J. Chen China, P. R. Co-Reduction Synthesis of Graphene/Au
Nanocomposite from Graphene
Oxide/Au3` Solution upon γ-Irradiation
18:10 A03-07 N. A. F.Othman Malaysia An Improved Method of Producing
Adsorbent for Metal Removal Using
Radiation Induced Graft Polymerization
18:20 A03-08 V. Luo China, P. R. Fabric Modification by Radiation Methods
19
Mon
ICARST–2017 Monday 24 April 2017
B03 16:30–18:30 Radiotracers for Industrial Processes
Venue: Room M2 Optimization and Safety I
Chair: Jovan Thereska (Albania)
TSec: Patrick Brisset (IAEA)
Time Id Presenter
16:30 B03-01 R.Alami Morocco Study by Radiotracer of a Phosphoric
Acid Production Line
16:45 B03-02 V. Yelgaonkar India Studying Flow Dynamics of Catalyst
Powder in CCU for Troubleshooting
17:00 B03-03 H. A.Affum Ghana The Application of CFD for Modelling
Flow and Visualization in a Cement Mill
and Experimental RTD Validation Using
Radiotracer Technology
17:15 B03-04 H. Ben Tunisia Radiotracers for Pulp Flow Dynamics
Abdelouahed Study in Three Different Phosphoric Acid
Reactors
17:30 B03-05 S. Sugiharto Indonesia Residence Time Distribution Study of
Geothermal Vapour Flow in Pipe Using
Axial Dispersion Modelling
17:45 B03-06 V. K. Sangal India Radiotracer Investigation of a Pulp and
Paper Mill Effluent Treatment Plant
—Discussion—
18:30–20:00 Welcome Reception
Venue: Rotunda
20
Mon
Tuesday 25 April 2017 ICARST–2017
A04 09:00–11:00 Radiation for Environmental
Venue: Board Room B/M1 Protection I
Chair: El-Sayed Hegazy (Egypt)
TSec: Sunil Sabharwal (IAEA)
Time Id Presenter
09:00 A04-01 E. Takács Hungary Ionizing Radiation Induced
Decomposition of Antibiotics in Waste
Water
09:20 A04-02 J.Wang China, P. R. Ionizing Irradiation-Induced Degradation
of PPCPs in Aqueous Solution
09:40 A04-03 S. Pillai USA Efficacy of Electron Beam Irradiation to
Address Emerging Microbial
Contaminants in Water Reuse
Programmes
10:00 A04-04 S. Borrely Brazil Toxicity Assays Applications for
Assessing Acute Effects for Radiation
Decomposition of Organics in Waters
10:20 A04-05 Y. Sun Poland Radiation Technology Application in
Environmental Protection
—Discussion—
Coffee break: 11:00–11:15
B04 09:00–11:00 Mitigating Climate Change: Protecting
Venue: Room M2 Coast Line and Environment
Chair: Catherine Hughes (Australia)
TSec: Patrick Brisset (IAEA)
Time Id Presenter
09:00 B04-01 C.Hughes Australia Radiotracer Methods for Understanding
Contaminant Dynamics in Aquatic
Environments
09:15 B04-02 D. Pham Van Bang France Nuclear Technologies Applied to
Sediment Transport in River, Estuarine
and Coastal Zones to Validate CFD Codes
09:30 B04-03 K. Bhar India Radiotracer Study to Investigate the
Spatial Dispersion Pattern of Dredged
Materials in Hooghly Estuary, West
Bengal, India
09:45 B04-04 J. Vianna Bandeira Brazil Technetium-99m: From Nuclear Medicine
Applications to Fine Sediment Transport
Studies
Continued. . .
21
Tue
ICARST–2017 Tuesday 25 April 2017
B04 continued. . .
Time Id Presenter
10:00 B04-05 P. Brisset IAEA The Use of Nucleonic Gauge JTTX in the
Port of Nantes Saint-Nazaire
10:15 B04-06 R. Suárez-Antola Uruguay Water Renewal in Montevideo’s Bay II:
A Compartmental Fractional Model for
Tritium Kinetics
10:30 B04-07 A. Ioannidou Greece The Radiotracer 7Be in Studying
Environmental Processes
—Discussion—
Coffee break: 11:00–11:15
A05 11:15–13:15 Advances in Radiation Chemistry
Venue: Board Room B/M1 Research I
Chair: Olgun Güven (Turkey)
TSec: Agnes Safrany (IAEA)
Time Id Presenter
11:15 A05-01 L.Wojnárovits Hungary Basic Radical Reactions in Water
Treatment by Ionizing Radiation
11:35 A05-02 M.Al-Sheikhly USA Synthesis of Novel Fabrics for Extraction
of Uranium from Seawater
11:55 A05-03 M.Mostafavi France Ultrafast Electron Transfer Studied by
Picosecond Pulse Radiolysis
12:15 A05-04 M.-C.Dubois- France Advances in Etched Ion-Track Polymer
Clochard Membranes for Environmental and
Microelectronic Applications
12:35 A05-05 S.Goldstein Israel Using Ionizing Radiation for Studying
Radical Reactions with Nitroxides:
Implications for their Biological Activity
12:55 A05-06 J. Barilla Czech Influence of N2O and Ethanol on the
Republic Chemical Stage of Radiobiological
Mechanism
13:05 A05-07 K.Marzouki Tunisia EPR Characterization of γ-Irradiated
Xerogels
Lunch break: 13:15–14:15
22
Tue
Tuesday 25 April 2017 ICARST–2017
B05 11:15–13:15 Radiotracers for Energy of the Future I
Venue: Room M2
Chair: Muthanna Al-Dahhan (USA)
TSec: Patrick Brisset (IAEA)
Time Id Presenter
11:15 B05-01 M.Al-Dahhan USA Liquid Holdup Studies in a Co-current
Gas-Liquid Upflow Moving Packed Bed
Reactor with Porous Catalyst Using γ-Ray
Densitometry
11:30 B05-02 V.Alexander USA Bed Expansion Studies in Upflow Moving
Catalytic Packed/Expanded Bed
Hydrotreating Reactor Using γ-Ray
Densitometry
11:45 B05-03 A.Chandra India Radioactive Tracing of an Industrial Scale
Continuous Pulp Digester
12:00 B05-04 D.Aquino Philippines Evaluating the Operating Conditions of a
Rectifier Column Using γ-Column
Scanning
12:15 B05-05 Q.Nguyen Huu Viet Nam γ-Scanning Technique as an Efficient
Investigation Tool for Diagnostics and
Troubleshooting in Industry: Case Studies
12:30 B05-06 C. P. K.Dagadu Ghana Validation of CFD Codes Using
Radiotracer RTD Analysis of Stirred
Vessels
—Discussion—
Lunch break: 13:15–14:15
A06 14:15–16:15 Dosimetry and Standards for Radiation
Venue: Board Room B/M1 Processing
Chair: Wilson A. P. Calvo (Brazil)
TSec: Bum Soo Han (IAEA)
Time Id Presenter
14:15 A06-01 A.Kovács Hungary Process Control Methods in Radiation
Technologies
14:35 A06-02 M. Bailey Denmark Dosimetry and Process Control for Using
Low Energy Electron Beams for
Sterilization or Decontamination of
Surfaces
14:55 A06-03 F. Kuntz France Is IQ/OQ/PQ Part of Irradiation Process
Control?
Continued. . .
23
Tue
ICARST–2017 Tuesday 25 April 2017
A06 continued. . .
Time Id Presenter
15:15 A06-04 Y. Zhang China, P. R. Dosimetry Standards and Dissemination
Systems for Radiation Processing in China
15:35 A06-05 S. Ebraheem Egypt EPR Dosimetry Systems; Assessment and
Developed in NCRRT
—Discussion—
Coffee break: 16:15–16:30
B06 14:15–16:15 Radiation Techniques for Energy of the
Venue: Room M2 Future
Chair: Rubens Martins Moreira (Brazil)
TSec: Patrick Brisset (IAEA)
Time Id Presenter
14:15 B06-01 I. M. Fernández Cuba The γ-Scanner: A Tool for the Quality
Gómez Control of the Process of Alcohol
Distillation
14:35 B06-02 T.Abd El Slam Egypt A New Method for Detecting Trace Oil
Concentration by Neutron Radiography
Technique
14:55 B06-03 C. Sebastian Calvo Peru Leaks Determinations in Reboilers from
Natural Liquid Fractioning Units
15:15 B06-04 L. Sabri USA RPT for Tracking Microalgae Cell
Movement in Split Photobioreactor
Column
15:35 B06-05 A. Toukan USA Flow Regime Identification in a
Co-Current Gas-Liquid Upflow Moving
Packed Beds Reactor Using γ-Ray
Densitometry
—Discussion—
Coffee break: 16:15–16:30
24
Tue
Tuesday 25 April 2017 ICARST–2017
A07 16:30–18:30 Advances in Radiation Chemistry
Venue: Board Room B/M1 Research II
Chair: Sara Goldstein (Israel)
TSec: Agnes Safrany (IAEA)
Time Id Presenter
16:30 A07-01 V. Feldman Russian Fed. The Radiation Chemistry of Organized
Systems: Basic Studies and Implications
16:50 A07-02 M. Jonsson Sweden Interfacial Radiation Chemistry in
Nuclear Technology
17:10 A07-03 C. I.Horak Argentina Radiation Sterilization of Devices and
Scaffolds for Tissue Engineering
17:30 A07-04 S. Korraa Egypt Effect of Sterilization by γ-Irradiation on
Biocompatibility of Starch-Based
Polymers and Composites Suitable for
Stem Cell Growth
17:50 A07-05 I. P. Kavirayani India Radiation Chemical Studies Leading to
the Development of Selenium
Radioprotectors
18:10 A07-06 O. Belyakov IAEA The IAEA Research on Radiation
Sterilization in Tissue Banking
S01 Chinese Mission Side Event
25
Tue
ICARST–2017 Tuesday 25 April 2017
B07 16:30–18:30 Radiotracers for Energy of the Future II
Venue: Room M2
Chair: Quang Nguyen Huu (Viet Nam)
TSec: Patrick Brisset (IAEA)
Time Id Presenter
16:30 B07-01 Z. Idiri Algeria Simulation and Optimization of a
Neutron Backscattering Analysis Set-Up
Using MCNP5 Code
16:45 B07-02 S.-H. Jung Korea, RPT Study on a Vertical Impeller Mixer
Rep. of
17:00 B07-03 A. Sultan USA Linear Attenuation Coefficients and Gas
Holdup Distributions of Bubble Column
with Vertical Internal Bundle for FT
Synthesis
17:15 B07-04 R.Alami Morocco Numerical Simulation of Measurement by
γ-Ray Scanning of Coke Deposition in
Packed Bad of Distillation Column
17:30 B07-05 S. Roy India Noninvasive Radiation Based
Densitometry and Velocimetric
Monitoring of Fluidization of Coal and
Bottom Ash Mixtures
17:45 B07-06 V.Khane USA Experimental Study of Pebble Flow
Dynamics in a PBMR Using RPT
—Discussion—
S01 Chinese Mission Side Event
26
Tue
Wednesday 26 April 2017 ICARST–2017
A08 09:00–11:00 Radiation Sources and Facilities: Panel
Venue: Board Room B/M1 Discussions
Chair: Suresh Pillai (USA)
TSec: Sunil Sabharwal (IAEA)
Time Id Presenter
09:00 A08-01 P.Dethier Belgium Review of the Two New Rhodotron
Accelerators: The Compact 10 MeV TT50
and the High Energy 40 MeV Rhodotron
09:20 A08-02 R.Wiens Canada A Billion Curies and Counting: Ensuring
60Co Supply and Disposal for Decades to
Come
09:40 A08-03 B.Han Korea, How to Apply Radiation Technology for
Rep. of Pollution Control
10:00 A08-04 A. Bryazgin Russian Fed. ILU Industrial Electron Accelerators
10:20 A08-05 W. Peng China, P. R. EB Technology vis-a-vis γ-Radiation for
Irradiation Sterilization: Emerging
Scenario
10:40 A08-06 A. K.Kohli India γ-Irradiator Technology: Challenges and
Future Prospects
Coffee break: 11:00–11:15
B08 09:00–11:00 Seeing the Invisible: Structure
Venue: Room M2 Imaging—Safe and Effective Industry I
Chair: Nicholas George Cutmore (Australia)
TSec: Patrick Brisset (IAEA)
Time Id Presenter
09:00 B08-01 N. G.Cutmore Australia Next-Generation Fast-Neutron/X-Ray
Scanner for Air Cargo Interrogation
09:20 B08-02 H. Ben Tunisia Monte Carlo Simulation and Experimental
Abdelouahed Verification of Blockages in Pipelines
Using γ-Ray Computed Tomography
09:40 B08-03 P. Cong China, P. R. Associated Image Processing Algorithm
in Dual-Projection Systems
10:00 B08-04 K. N.Myaing Myanmar Comparison of Image Reconstructions for
γ-Transmission Computed Tomography
System by Using MATLAB and i-Gorbit
Software
Continued. . .
27
Wed
ICARST–2017 Wednesday 26 April 2017
B08 continued. . .
Time Id Presenter
10:20 B08-05 T. D.Dang Nguyen Viet Nam Gorbit – The Flexible γ-Computed
Tomography System for Pipeline
Inspection
—Discussion—
Coffee break: 11:00–11:15
A09 11:15–13:15 Preservation of Cultural Heritage
Venue: Board Room B/M1
Chair: Pablo Vasquez (Brazil)
TSec: Sunil Sabharwal (IAEA)
Time Id Presenter
11:15 A09-01 J.Havermans Netherlands Disinfection and Consolidation of
Archived Materials and Cultural Heritage
Artefacts by Radiation Processing
Techniques
11:35 A09-02 B.Katušin-Ražem Croatia Irradiation Method in the Protection of
Cultural Heritage Objects Endangered by
Massive Biodegradation
11:55 A09-03 I. V.Moise Romania Radiation Processing for Cultural
Heritage Preservation: Romanian
Experience
12:15 A09-04 Q.-K. Tran France Development of New Radiation-Curing
Monomers-Resins Systems for the
Consolidation of Wooden Cultural
Heritage Artefacts
12:35 A09-05 A.Cemmi Italy Application of Ionizing Radiation for
Cultural Heritage
12:55 A09-06 L. Cortella France Uses and Prospects in γ-Biocide
Treatments for Cultural Heritage
Lunch break: 13:15–14:15
28
Wed
Wednesday 26 April 2017 ICARST–2017
B09 11:15–13:15 Radiotracer for Managing Natural
Venue: Room M2 Resources
Chair: Rachad Alami (Morocco)
TSec: Patrick Brisset (IAEA)
Time Id Presenter
11:15 B09-01 S.Mimount Morocco Development of Radiometric Methods for
Optimization of Phosphate Transport
Process by “Slurry Pipe”
11:30 B09-02 F.Diaz Chile Determination of Mineral Behaviour in
Ball Mills at Chilean Copper Minning
Using Radioactive Tracers
11:45 B09-03 M.Rogowski Poland Radiotracer Methods for Ore and
Flotation Tailings Leaching
12:00 B09-04 H. J. Pant India Radiotracer Investigation in an
Industrial-Scale Fluid Catalytic Cracking
Unit
12:15 B09-05 J. Tickner Australia Developing a Commercial Facility for
Rapid Assay of Gold and other Elements
in Mineral Ores Using γ-Activation
Analysis
12:30 B09-06 R. M.Moreira Brazil A Tracer Application in Detecting
Damage to Oil Industry Piping
—Discussion—
Lunch break: 13:15–14:15
29
Wed
ICARST–2017 Wednesday 26 April 2017
PA1 Irradiation Facilities and their
Venue: A–Building Applications
Chair:Mark Bailey (Denmark)
TSec: Sunil Sabharwal (IAEA)
PA1-01 A.Abaza Egypt New Trends in Radiation Dosimeters
PA1-02 S.Abdelgawad Egypt Setting up of New Radiation Facilities in
Alexandria, Egypt
PA1-03 J.Abdullah Malaysia In Situ and Non-Destructive Detection of
Oleoresin in Standing Agarwood Trees Using
Portable γ-Ray Tomography Imaging System
PA1-04 A.Adjerad Algeria Facilitating Sustainable Education in Nuclear
Science and Technology
PA1-05 F.Djouider Algeria Pilot-Scale Study of the Radiation-Induced
Silica Removal from Underground Brackish
Water in Saudi Arabia
PA1-06 A.Cemmi Italy Radiation Activities at ENEA Calliope
γ-Facility
PA1-07 J. Kim Korea, Detoxification of High Toxicity Substances by
Rep. of Radiation Transformation Technique
PA1-08 K. Bergaoui Tunisia Evaluation of Radiation Shield Integrity of DD
Neutron Generator Facilities by Monte Carlo
and Experimental Methods
PA1-09 R. Betesho Babrud I. R. Iran Fungal Decontamination of Historical Oil
Painting by Using γ-Ray
PA1-10 R. Betesho Babrud I. R. Iran The Study of γ-Ray Efficiency in Converting
Tehran Municipal Sewage Sludge into a
Sanitary Fertilizer
PA1-11 C. A. D.Carvalho Brazil The Application of Radiochemical and Isotopic
Filho Studies to Inform on the Impact of Acidic
Effluent Discharges from the Caldas Uranium
Mine into Neighboring Surface Waters
PA1-12 D.Chmielewska- Poland Application of Electron Beam for Preservation
Śmietanko Biodeteriorated Cultural Heritage Paper-Based
Objects
PA1-13 L.Coretchi Moldova, Using of Radiation Sterilization
Rep. of
PA1-14 M. L.Costa Brazil Relevant Safety Aspects for Radioactive Tracers
in Industrial Process
PA1-15 F.Djouider Algeria Radiation Induced Environmental Remediation
of Toxic Cr(VI) Heavy Metal in Aerated Neutral
Solution under Simulated Industrial Effluent
PA1-16 A.Docters Argentina Intergrating Management Systems to Good
Irradiation Practices within a Framework of
Social Responsibility
Continued. . .
30
Wed
Wednesday 26 April 2017 ICARST–2017
Id Presenter
PA1-17 S. E. Eid Egypt ESR Dosimetric Properties of Sodium
Glutamate
PA1-18 R. El-Motaium Egypt Ionizing Radiation as a New Technique for
Treating Sewage Wastewater and Sludge in
Arid Regions
PA1-19 K. Farah Tunisia EPR Characterization of a Medical Grade
Polyethylene for High Dose Dosimetry
PA1-20 M. Fulop Slovakia Treatment of Organic Pollutants Based on PCB
in the River Sediment by Electron Beam
PA1-21 E. Furuta Japan A New Fluorescence Detection Method with
Plastic Scintillators Using a Conventional
LSC-Organic Waste Less Method
PA1-22 F.Gao China, P. R. Optimal Design of 60Co Single Source
Radiation Facility with Monte Carlo Method
PA1-23 J. R.George India Conceptual Development of an Irradiator for
Cross-Linking of Cables Using 60Co γ-Rays
PA1-24 R.Gomes Brazil Assessment of Safety Systems Design of
Industrial Irradiation Facilities in Brazil
PA1-25 S.Goswami India Measurement of Residence Time Distribution
of Wastewater in a Constructed Wetland
System Using Radiotracer Technique
PA1-26 U.Gryczka Poland Application of Low Energy Electron Beam in
Microbiological Decontamination Process
PA1-27 A. Ihsan Pakistan Core Neutronic and Source Strength Analyses
of 60Co Production in Local Power Reactors
PA1-28 B. S. Jang Korea, RI-Biomics Technology for the Advance
Rep. of Radioisotope Application in Modern Life
PA1-29 S. Yu Korea, Effect of γ-Ray and Electron Beam Irradiation
Rep. of on Reduction of Graphene Oxide Suspension in
Aqueous Alcoholic Solution
PA1-30 W.-G.Kang Korea, Radiation Shielding Analyses of a 10 MeV
Rep. of LINAC for Electron Beam and X-Ray at KACST
PA1-31 Y.Karakirova Bulgaria Optimizing the Size and Composition of Solid
State/EPR Dosimeters
PA1-32 S. Yu Korea, Degradation Characteristics and
Rep. of Transformation Products of Iodinated Contrast
Media Using Ionizing Radiation
PA1-33 S. Ladjouzi Algeria Structural Characterization of γ Irradiated
GdBO3/Silica Composite Obtained by Sol Gel
Process
PA1-34 K. K. Lay Myanmar Research on Conversion of Natural Wastes to
Useful Products by Application of Radiation
Processing for Agricultural Sector of Myanmar
Continued. . .
31
Wed
ICARST–2017 Wednesday 26 April 2017
Id Presenter
PA1-35 G. Liu China, P. R. Dose Increase System in a γ-Irradiator
PA1-36 K. Y. Lwin Myanmar Human Resource Development for the
Application of Radioisotope Techniques to
Industry in Myanmar
PA1-37 S. Cabo Verde Portugal Application of Ionizing Radiation for Treatment
and Valorization of Cork Wasterwater
PA1-38 B.Mihaljević Croatia Detoxification of Aflatoxin B1 and Ochratoxin A
by γ-Radiation
PA1-39 S.Mimount Morocco Dosimetric Evaluation in Industrial
Gammagraphy Operations
PA1-40 W.Mohamed Egypt Application of Isotopic Techniques Using
Moustafa Mathematical Models in Environmental Process
PA1-41 V.Morgunov Ukraine The Numerical Simulation of Cultural Heritage
Radiation Treatment by Monte Carlo Method
PA1-42 M.Mouhib Morocco Upgrading of 60Co in Temporary Pool for Dry
Storage Irradiation Facility SIBO INRA/Tangier
Morocco
PA1-43 M.Mouhib Morocco Enhancing Safety and Control Features of
Radiation Processing Facility SIBO
INRA/Tangier Morocco
PA1-44 L.Ounalli Mejri Tunisia The Efficiency of Radiation Processing by the
Tunisian 60Co Industrial Irradiator after 16
Years of Use
PA1-45 H. J. Pant India Measurement of Voidage/Holdup in Industrial
Process Systems Using γ-Ray Densitometry
PA1-46 E. F. Prieto Miranda Cuba Dosimetric Characterization of the
ISOGAMMA LLoCo Irradiator
PA1-47 I. Pucić Croatia γ-Irradiation in Protection of Cultural Heritage:
Effects on Model Cellulose Based Textiles
PA1-48 B.Mihaljević Croatia Dosimetric Calibration of a Panoramic 60Co
γ-Ray Source
PA1-49 M.Rushdi Sudan EPR Dosimetric Potential of Ammonium
Oxalate Monohydrate in Radiation Technology
PA1-50 F. Salgado Ecuador Development of a Digital Model for the
Dosimetry of the 60Co Irradiator at the
National Polytechnic School of Ecuador
PA1-51 M. Šegvić Klarić Croatia γ-Irradiation for Cultural Heritage: Treatment
of Selected Fungi on Linen Textile
PA1-52 B. R. Shah Nepal Personal Radiation Dosimetry at Radiological
Facilities, Nepal
PA1-53 S. Yu Korea, Electron Beam Techniques for Air Pollution
Rep. of Control
Continued. . .
32
Wed
Wednesday 26 April 2017 ICARST–2017
Id Presenter
PA1-54 D. Souza Brazil Dosimetric Properties of MgB4O7:Ce and
MgB4O7:Ce, Li for Thermoluminescence
Dosimetry Applications
PA1-55 A. Tegze Hungary Radiolysis Induced Degradation of
Fluoroquinolones
PA1-56 M. H. Trabelsi Tunisia Tunisian Experience Assessment of Installing a
Pilot 60Co Source for Irradiation
PA1-57 A. Tripathi India γ-Radiation-Co-Cryogelation Induced
Synthesis of Macroporous rpCryogels for
Bioengineering Applications
PA1-58 P.Vasquez Brazil Kinetics of Free Radicals Decay Reactions in
Cellulosic-Based Heritage Materials Disinfected
by γ-Radiation
PA1-59 M. V.Vogt Argentina Feasibility of Using Irradiation to Degrade a
Toxic Dye Compound
PA1-60 A.Weidauer Germany Toroidal Electron Source
PA1-61 A.Zaouak Tunisia γ-Radiation Induced Decolouration and
Degradation on Aqueous Solutions of Indigo
Carmine Dye
PA1-62 Z. Zimek Poland Electron Accelerator for R&D Study and
Radiation Processing
PB Radiation Technologies for
Venue: A–Building Measurement
Chair: Haifa Ben Abdelouahed (Tunisia)
TSec: Patrick Brisset (IAEA)
PB-01 A. O. A.Abdelbari Sudan The Study of Industrial Process with
Radioactive Tracer RTD Method Enhanced
System Analysis
PB-02 J. K. J. Al-Saedi Iraq The Concentrations of Major and Trace
Elements in Powdered Milk Using XRF and
NAA, and Comparison to Other Techniques
PB-03 R.Alami Morocco Development of a New Ambient Dosimetry
Monitor for In Situ Environmental Monitoring
at the Nuclear Studies Centre of Maâmora,
Morocco
PB-04 K. Broce Panama Study of Sediments in a Sub-Basin of the
Panama Canal Using Nuclear Techniques
PB-05 M. J. G.Gichuru Kenya Tracers of High Altitude Pollution Sources and
Impact on Mt. Kenya Ecosystem
PB-06 M.Goes Nunes Brazil CaSO4:Dy and CaSO4:Ce,Eu Intrinsic
Efficiencies Dependence on Ionizing Radiation
Type and Quality
Continued. . .
33
Wed
ICARST–2017 Wednesday 26 April 2017
Id Presenter
PB-07 C. C. Bueno Brazil Evaluation of TL and OSL Response of
CaF2:Tm for Electron Beams Dosimetry in
Radiation Processing
PB-08 J. D. R. LopesGomesBrazil Radiation Shielding Design Assessment of
Nucleonic Gauges
PB-09 A. H. Lopez Brazil Axial Computed Tomography Phase-Space
Gonzales Source Model in the PenEasy/PENELOPE
Monte Carlo System: Implementation and
Validation
PB-10 U.Mirsaidov Tajikistan Application of Radiation Science and
Technology in the Republic of Tajikistan
PB-11 M. S.Mohammed Sudan Simulation Studies on the Image Quality of
Industrial Film Radiography
PB-12 K. N.Myaing Myanmar Comparison of Image Reconstructions for
γ-Transmission Computed Tomography System
by Using MATLAB and i-Gorbit Software
PB-13 H. K.Namburi Czech Neutron Radiography Studies for Detection of
Republic Hydrogen Distribution in Nuclear Fuel
Claddings at Research Centre Řež
PB-14 J. Phirani India Adsorption Behaviour of Chloroauric Acid, a
Generic Adsorbing Tracer, for Finding Wetting
Behaviour of Fluids in Oil and Gas Industry
PB-15 A.Quaranta Italy Ion Irradiation Effects on the Optical Properties
of Quantum Dots for Nano-Dosimetric Systems
PB-16 M.Rodríguez Cuba Results of Radiation Protection in Practices
Alayón with Sources of Ionizing Radiation in the
Petroleum Refining Industry
PB-17 M. I. A. Sagiroun Sudan Radiation Dosimetry of Laboratory Practices
based on Radiotracers Techniques
PB-18 R.Koos Germany Application of Complementary Beam
Techniques to Study Deformation Mechanisms
in Heterogeneous Materials for Automotive
Industry
PB-19 L. Sereeter Mongolia Neutron Activation Installments for Control of
Flour Spar Enriching Factory in Mongolia
PB-20 T. Smolinski Poland Synthesis Method of Multimodal Radiotracers
for Industrial Processes and Environmental
Research
PB-21 S. Sugiharto Indonesia Examination the Performance of the Trayed
Ethylen Production Column Using γ-Ray Scan
Techique
Continued. . .
34
Wed
Wednesday 26 April 2017 ICARST–2017
Id Presenter
PB-22 I. D. A. Sutapa Indonesia Resident Time Determination of IPAG60 in
Order to Increase Efficiency of Drinking Water
Treatment Plant for Peatland Area
PB-23 T.Weerakkody Sri Lanka Terrestrial Background Radiation in
Appuhamillage Norochcholai in the North Western Coast of Sri
Lanka
A10 16:30–18:30 Development in Electron Accelerators
Venue: Board Room B/M1 Technology
Chair: Lixin Shen (China)
TSec: Bum Soo Han (IAEA)
Time Id Presenter
16:30 A10-01 Y. Zhang China, P. R. Addressing Challenges Posed by Electron
Beam Irradiation through Innovation
16:50 A10-02 C.Cooper USA Illinois Accelerator Research Center
17:05 A10-03 T.Kroc USA A Compact Superconducting RF
Accelerator for Electron Beam and X-Ray
Irradiation
17:20 A10-04 F.-H. Roegner Germany Low-Energy Electron Irradiation for Novel
Applications in Medical Production and
Pharma
17:35 A10-05 Withdrawn
17:50 A10-06 N.Kuksanov Russian Fed. DC ELV Accelerators: Development and
Application
18:05 A10-07 A.Weidauer Germany Electron Treatment of Seed
—Discussion—
S02 ISTRA Side Event
35
Wed
ICARST–2017 Wednesday 26 April 2017
B10 16:30–18:30 Radiotracers for NewMaterials
Venue: Room M2 Development
Chair: Gerardo Maghella (Peru)
TSec: Patrick Brisset (IAEA)
Time Id Presenter
16:30 B10-01 H.Makil France Quality Control of Neutron-Absorber
Materials for the Nuclear Fuel Cycle:
Principle of the JEN_3 Neutron
Backscattering Gauge
16:50 B10-02 A.Kleinrahm Germany Radionuclide Technique in Mechanical
Engineering: A Powerful Measuring
Method for Tribological Tasks —
Installations at and Services of ZAG
Zyklotron AG
17:10 B10-03 B.Artemiev Russian Fed. Replacing the Isotopic Radiation Sources
in Thickness Measurement on X-Ray
17:30 B10-04 F.Ditrói Hungary Development of Thin Layer Activation for
Wear Measurement
17:50 B10-05 W. A. P. Calvo Brazil Industrial Applications of the IEA-R1
Research Reactor in Brazil
—Discussion—
S02 ISTRA Side Event
36
Wed
Thursday 27 April 2017 ICARST–2017
A11 09:00–11:00 Safety and Security Perspectives of
Venue: Board Room B/M1 Radiation Facilities
Chair: András Kovács (Hungary)
TSec: Sunil Sabharwal (IAEA)
Time Id Presenter
09:00 A11-01 M. Frenzel Germany Upgrading Safety and Security of
γ-Irradiation Facilities: Possibilities and
Limitations
09:20 A11-02 F. Schmitz Belgium Safety Improvements of an Industrial
Irradiation Facility
09:40 A11-03 M.Alcerreca Mexico Upgrading and Continuous Improvement
of ININ γ-Irradiation Facility
10:00 A11-04 M.Mouhib Morocco Enhancing Nuclear Security System of
Irradiation Facility SIBO INRA/Tangier
Morocco
10:20 A11-05 G. Yu China, P. R. Development and Application of Electron
Linear Accelerator of CIAE
—Discussion—
Coffee break: 11:00–11:15
B11 09:00–11:00 Seeing the Invisible: Structure
Venue: Room M2 Imaging—Safe and Effective Industry II
Chair: Ghiyas Ud Din (Pakistan)
TSec: Patrick Brisset (IAEA)
Time Id Presenter
09:00 B11-01 G.Ud Din Pakistan Investigation of Two-Phase Flow
Behaviour Across a 90 Degree Horizontal
Bend: CFD Simulation and γ-Computer
Tomography Validation
09:15 B11-02 J.-H. Jin Korea, New Developments on the Automatic
Rep. of γ-Column Scanner
09:30 B11-03 H. J. Pant India Radiotracer Applications in Industry and
Environment
09:45 B11-04 G. A. Johansen Norway Tomographic Methods for Multiphase
Flow Measurement
Continued. . .
37
Thu
ICARST–2017 Thursday 27 April 2017
B11 continued. . .
Time Id Presenter
10:00 B11-05 G.Maghella Peru Determination of Interfaces in Packed
Columns by Using Sealed Sources
10:15 B11-06 A. Saadaoui Morocco A γ-Ray Computed Tomography for
Investigating the Wood Structure
—Discussion—
Coffee break: 11:00–11:15
A12 11:15–13:15 Radiation for Environmental
Venue: Board Room B/M1 Protection II
Chair: Erzsebet Takács (Hungary)
TSec: Sunil Sabharwal (IAEA)
Time Id Presenter
11:15 A12-01 S. Cabo Verde Portugal Virucidal Potential of γ-Radiation
11:35 A12-02 S.Mezyk USA Removal of Wastewater Pharmaceutical
Chemical Contaminants Using AOPs
11:55 A12-03 M.-H.Wu China, P. R. Applications of Radiation Technology in
Control and Treatment for Environmental
Pollution
12:15 A12-04 S. Yu Korea, Application of Mobile Electron Beam for
Rep. of Remediation of Soil and Groundwater
Contaminated with Leachate from
Animal Carcass Burial Sites
12:35 A12-05 S. Pillai USA Electron Beam Treatment for Potable
Water Reuse: Removal of Bromate and
Perfluorooctanoic Acid
12:55 A12-06 G. Sági Hungary Changes in the Biological Degradability
and Toxicity of Sulfonamide Antibiotics in
Activated Sludge and River Water due to
Ionizing Radiation Treatment
Lunch break: 13:15–14:15
38
Thu
Thursday 27 April 2017 ICARST–2017
B12 11:15–13:15 Radiation Techniques for Industrial
Venue: Board Room B/M1 Processes Optimization and Safety II
Chair: Geir Anton Johansen (Norway)
TSec: Patrick Brisset (IAEA)
Time Id Presenter
11:15 B12-01 J. Thereska Albania Radiotracer Residence-Time Distribution
Method in Diagnosing Industrial
Processing Units: Case Studies
11:30 B12-02 J. S. Rawat India Investigation of the Multiple Side
Injections on Hydrodynamics of the
Gas-Solids Fluidized Bed Using
Radiotracer Based Techniques
11:45 B12-03 G.Ud Din Pakistan Radiotracer and Sealed Source
Technologies for Measurements in
Industry
12:00 B12-04 K. El Korchi Morocco Radioisotope Techniques for Detection of
Coking in Liquid Flow through a Solid
Phase in a Lab-Scale Distillation Column’s
12:15 B12-05 S.Goswami India Measurement of Residence Time
Distribution of Wastewater in a
Constructed Wetland System Using
Radiotracer Technique
12:30 B12-06 I. I.Mumuni Ghana Radiotracer Investigation of the Effect of
Impeller Type on Mixing in Industrial
Process Simulator
—Discussion—
Lunch break: 13:15–14:15
39
Thu
ICARST–2017 Thursday 27 April 2017
B13 14:15–16:15 Radiotracer for Managing of Natural
Venue: Room M2 Resources, Energy and Processes
Chair: Jefferson Vianna Bandeira (Brazil)
TSec: Patrick Brisset (IAEA)
Time Id Presenter
14:15 B13-01 T. B. O. Jentsch Germany Investigation of Heavy Metal Release at a
Municipal Solid Waste Incineration
Facility: An Excellent Example for the
Unique Potential of Intrinsic Radiotracer
Application to the Investigation of
Industrial Processes in Chemical
Engineering
14:35 B13-02 J. Abdullah Malaysia Radiotracer Investigation in an Aeration
Tank of a Waste Water Treatment Plant
14:55 B13-03 R.Alami Morocco Data Fusion Approach for Improving the
Reliability of Radiographic Testing and
other Complementary NDT Techniques
15:15 B13-04 I. I.Mumuni Ghana Neutron Backscatter Technique as an
Alternative Method for Quality Assurance
and Standardization of Petroleum
Products
15:35 B13-05 M. P.Hlaing Myanmar Identification of the Internal Condition of
Crude Oil Distillation Unit Using
γ-Column Scanning Technique in
Myanmar
—Discussion—
40
Thu
Thursday 27 April 2017 ICARST–2017
PA2 Radiation Creation of Materials
Venue: A–Building from Fundamentals to Application
Chair: Laszlo Wojnárovits (Hungary)
TSec: Agnes Safrany (IAEA)
PA2-01 S.Abdelrehim Egypt Developing a Simple Method Using Ionizing
Radiation to Produce Polyacrylic Acid Based
Nanoparticles
PA2-02 Y.Aguilera- Cuba Synthesis by γ-Radiation and Characterization
Corrales of Poly(Vinylpyrrolidone) Nanogel
PA2-03 M. K. Pramanik Bangladesh Application of γ Radiation and
Physicochemical Treatment to Improve the
Bioactive Properties of Chitosan Extracted from
Shrimp Shell
PA2-04 M. C.Anessi Argentina Predicting the Behaviour of a Biomaterial as
Bone Replacement
PA2-05 I. C. Calina Romania Electron Beam Synthesis of Inulin Hydrogels
Extracted from Helianthus Tuberosus L.
PA2-06 J. Cardoso Brazil Recycled HDPE/Vulcanized EPDMMixtures
Obtained by Irradiation Processes
PA2-07 K. R. C.De Silva Sri Lanka Determination of the Radiation Dose Required
to Obtain Desired Viscosity Average Molecular
Mass Using Commercially Available Chitosan
and Signification of this Technique in its
Applications
PA2-08 E. Eisawy Egypt The Effect of Radiation Environment on
Electrical Insulation Materials
PA2-09 N. El-Sawy Egypt Radiation Synthesis of Acrylic Acid onto
Poly(tetrafluoroethylene-perfluorovinyl ether)
Film: Chemical Modifications and Electrical
Conductivity
PA2-10 N. Farahat Egypt Sorption of Iodine on Ion Exchange Resins
VPAer2d-e11 L. M. Ferreira Portugal Distinct Polymeric Based Materials
Prepared/Functionalized by γ-Irradiation for
Biomedical Applications and Roman Mosaics
Preservation
PA2-12 L.Garcia- Mexico Synthesis of Cross-Linking Films Based of
Uriostegui 3-(Trimethoxysilyl) Propyl Methacrylate
Silanized Xanthan Gum/Lignin and their
Cross-Linking by γ-Radiation, to Potential
Application and Films Packing
PA2-13 X. W.Ge China, P. R. Monodispersed Polypyrrole Nanoparticles
Prepared via Water Padiolysis and their
Photothermal Therapy on Cancer Cells
Continued. . .
41
Thu
ICARST–2017 Thursday 27 April 2017
Id Presenter
PA2-14 A.Geraldo Brazil Obtention and Characterization of γ-Irradiated
Recycled HDPE/EPDDM Blends
PA2-15 S. Ismail Egypt γ-Radiation Enhancement of Photocatalytic
Activity of Conducting Polyaniline-TiO2
Nanocomposites for Degradation of Methyl
Orange Dye under Visible Light Irradiation
PA2-16 T. Jurkin Croatia Radiolytical Synthesis and Mechanism of Gold
Nanoparticle Formation
PA2-17 M.Kaci Algeria Functional Properties and Ecotoxicity of
Bionanocomposites Based on PHBV/PLA
Blend under Electron Beam Irradiation
PA2-18 I. U.Khan Pakistan Studying the Biological Efficacy of
Radiation-Treated Radiolabelled
DOTA-Bombesin-Decorated Nanoconstructs as
Potential Nanosized Drug Delivery Systems
PA2-19 S. Yu Korea, Fabrication of Advanced Soft Magnetic
Rep. of Nanomaterials Using the Radiation
PA2-20 G. H. C.Varca Brazil Development of Advanced Scaffolds and
Polymeric Systems for Improved Cell and
Tissue Growth
PA2-21 J. Krstić Serbia Mechanical Characteristics and Antibacterial
Properties of Ag-Poly(Vinyl
Alcohol)/ws-Chitosan Hydrogel
Nanocomposites Synthesized by γ-Irradiation
Combined with Freeze/Thaw Cycles
PA2-22 J. Li China, P. R. Dyestuff Free: Colouring Fabrics by Graft
Polymerization
PA2-23 D. Lucan Romania Influence of the Coolant Chemistry on the
Structural Materials Surfaces Exposed into the
Candu NPP Primary Circuit
PA2-24 E.-M. Lungulescu Romania Radiation-Induced Oxidation in γ-Irradiated
UHMWPE Modified with Hydroxyapatite
PA2-25 J.Madrid Philippines Optimization of Electron Beam-Induced
Synthesis of Polypropylene-g-poly(Glycidyl
Methacrylate) for Cr(VI) and Cd(II) Adsorption
Using Full Factorial Design
PA2-26 G.Mahmoud Egypt Radiation Development of (Polyvinyl
Pyrrolidon/Acrylic Acid)- Silver
Nanocomposite for the Disposal of Phenolic
Compounds from their Aqueous Solutions
PA2-27 A.Mahmoud Sudan A Comparative Study of Radiation Sterilization
of Cell Culture Media and Filtration
Sterilization Method in Cell Culture Laboratory
Continued. . .
42
Thu
Thursday 27 April 2017 ICARST–2017
Id Presenter
PA2-28 H. Bhunia India Simultaneous Radiation Grafting of Acrylic
Acid on Polypropylene Films: Optimization,
Biodegradability and Evaluation of
Ecotoxicological Impact
PA2-29 K.Marušić Croatia Metal Surface Modification with Fatty Acids
Using Ionizing Radiation
PA2-30 K.Marzouki Tunisia Irradiation Effects on Structure and
Spectroscopic Properties of Sugar Doped
Sol-Gel Silica
PA2-31 S.Mohd Janib Malaysia Ionizing Radiation Engineered Functional
Nanogels for Biomedical Applications
PA2-32 M. Z. I.Mollah Bangladesh Effect of γ-Radiation on the Physico-Mechanical
Properties of Gelatin-Based Films and
Jute-Reinforced Polymer Composites
PA2-33 M.Negrin Italy Ionizing Radiation as a Tool to Affect Polymer
Biodegradation
PA2-34 N. G.Nik Salleh Malaysia Development of Nanocomposite Coatings by
Radiation Curing
PA2-35 H.Nizam El-Din Egypt Swelling and Drug Release Kinetics of
Polyacrylamide/Sodium Alginate Copolymer
Hydrogels Synthesized by γ-Irradiation
PA2-36 R. Papaléo Brazil Effect of Spatial Confinement on the Radiolytic
Efficiency of High-Energy Ions in Polymers
PA2-37 A.Ortega Mexico Functionalization of Polypropylene Films with
Glycidyl Methacrylate by γ-Radiation
PA2-38 M. P. Pérez-Calixto Mexico Synthesis and Characterization of PP Films
Rich in Primary Amines for Cell Cultures, by
γ-Radiation
PA2-39 T. Piroonpan Thailand Biopolymer-Silver Nanoparticle as a CIELAB
Colour Space Dosimeter
PA2-40 I. Pucić Croatia Nanocarbon Based
PolyLY(Ethylene-Terephthalate)
Nanocomposites and Various Irradiations
PA2-41 A.Raafat Egypt In Situ Deposition of Nanohydroxyapatite
within N,O-Carboxymethylchitosan/
Polyvinylpyrrolidone Hydrogels:
Characterization and Bioactivity Evaluation
PA2-42 A.Radosavljević Serbia Morphological, Physico-Chemical and
Mechanical Properties of Radiolytically
Synthesized Nano-Ag/
poly(N-isopropylacrylamide) Hydrogels
Continued. . .
43
Thu
ICARST–2017 Thursday 27 April 2017
Id Presenter
PA2-43 N.Rahman Bangladesh Preparation of Selective Hazardous Metal Ion
Adsorbents from Acrylic Monomer Grafted
PET Films
PA2-44 M.Rapado Cuba Nanogels of Polyvinylpyrrolidone Obtained by
Paneque γ-Radiation: Physicochemical and Biological
Characterization
PA2-45 S. Y. Ratnayake Sri Lanka Chemical Reduction of Nitrate by Zerovalent
Iron Nanoparticles Adsorbed Radiation Grafted
Copolymer Matrix
PA2-46 A. Sagatova Slovakia Lifetime Study of Electronic Devices for
Extreme Radiation Conditions
PA2-47 F. Saghatchi I. R. Iran The Hormetic Effect of X-Rays on Biosynthesis
of Gold Nanoparticles by Actinobacteria
PA2-48 M. Salla Ferreira Brazil Correlation of Traditional and One-Step
Irradiation Process for Chitosan Production
from Charybdis Hellerii Crab Shells
PA2-49 H. Sayed Sudan Effect of γ-Irradiation on the Molecular Weight
and Structure of Guar Gum
PA2-50 S. Shayanfar USA Investigations on Immobilizing Anthocyanin
and Betacyanin onto Polyethylene Films
PA2-51 N. A. Shukri Malaysia Shelf Life Assessment of Sliced Bread by Sorbic
Acid Based Active Film
PA2-52 Z.Kačarević- Serbia Structural Characterization, Antibacterial
Popović Properties and Citotoxicity of γ-Irradiation
Synthesized Ag-poly(N-isopropylacrylamide/
itaconic acid) Hydrogel Nanocomposites
PA2-53 I. Tartaro Bujak Croatia The Effect of Natural Antioxidiants in Thiyl
Radical-Induced Lipid Modification Processes
PA2-54 T. M. Ting Malaysia Evaluation of Thorium Adsorbent Prepared by
Radiation Grafting and Functionalization with
Glucamine
PA2-55 M.Wang China, P. R. γ-Ray-Radiation-Scissioned Chitosan as a Gene
Carrier and its Improved in vitro Gene
Transfection Performance
PA2-56 Y. Yin China, P. R. In Situ Compatibilization of Polyblends and
Polymer Based Composites Induced by
γ-Irradiation
PA2-57 S. Yu Korea, Low Dimensional Nanomaterials-Based
Rep. of Interfacial Engineering in Organic Solar Cells
PA2-58 T. Zaharescu Romania Radiochemical Stability and Life Time of
LDPE-Based Flexible Composite Filled with
Ce-Doped PZT-PbZrTiO3
Continued. . .
44
Thu
Thursday 27 April 2017 ICARST–2017
Id Presenter
PA2-59 A.Zaouak Tunisia Decolouration and Degradation of Erythrosine
by γ-Irradiation
PA2-60 H.-L.Ma China, P. R. γ-Ray Induced Reduction and Modification of
Graphene Oxide
A13 16:30–18:30 Advanced Nano Materials
Venue: Board Room B/M1
Chair: Piotr Ulański (Poland)
TSec: Agnes Safrany (IAEA)
Time Id Presenter
16:30 A13-01 C.Dispenza Italy Radiation Synthesis of Nanosized Drug
Delivery Devices
16:50 A13-02 M.Grasselli Argentina Protein-Based Nanoparticles Prepared by
Radiation-Induced Cross-Linking
17:10 A13-03 W. Pasanphan Thailand Molecular Design and Synthesis of
Different Polymer-Based Nanoparticles as
Nanocarriers Using Irradiation
Techniques
17:30 A13-04 K. V.Katti USA Green Nanotechnology in Nuclear
Medicine: Tumor Specific Radioactive
Gold Nanoparticles for New Approaches
in Cancer Therapy
17:50 A13-05 G. H. C.Varca Brazil State of the Art and Current Advances on
Protein Cross-Linking by Irradiation:
Protein Based Nanocarriers and Bioactive
Nanoparticles
18:10 A13-06 Y. Bondar Ukraine Radiation-Chemical Synthesis of
Nanocomposite Adsorbents Based on
Polypropylene Fibres for Selective
Removal of Heavy Metals and
Radionuclides
18:20 A13-07 A. Salih Sudan Preparation of Polyurethane Acrylate/
Organically Modified Montmorillonite
Nanocomposites by Electron Beam
Radiation Curing
45
Thu
ICARST–2017 Thursday 27 April 2017
B14 16:30–18:30 Radiation for Cultural Heritage
Venue: Room M2 Characterization
Chair: Jean Louis Boutaine (France)
TSec: Patrick Brisset (IAEA)
Time Id Presenter
16:30 B14-01 J. L. Boutaine France A Survey of the Possibilities of Various
Radiographic Techniques for the Non
Destructive Examination of Cultural
Heritage Artefacts
16:45 B14-02 M. J. G.Gichuru Kenya Application of Ionizing radiation in
Studying Akaba and Masai Art Objects
Made from Glass
17:00 B14-03 Ş. Ekinci Turkey Radiographic Investigation of
Archaeological Objects
17:15 B14-04 B.Artemiev Russian Fed. Using X-Rays to Detect Hidden Images
(Old Masters) on Priming Canvases
17:30 B14-05 R.Alami Morocco Some Applications of X-Rays in the
Service of the Archaeological Site of
Volubilis
17:45 B14-06 F.De Beer South Africa Secrets and Mysteries of our Past
Revealed by Neutron and X-Ray
Radiography/Tomography
18:00 B14-07 R.Alami Morocco The Radiography in the Service of the
Preservation of the Moroccan Historical
Heritage
—Discussion—
46
Thu
Friday 28 April 2017 ICARST–2017
A14 09:00–11:00 Technical Cooperation Success Stories
Venue: Board Room B/M1
Chair: Luis Carlos Longoria Gandara (IAEA)
TSec: Sunil Sabharwal (IAEA)
Time Id Presenter
09:00 A14-01 B.Mihaljević Croatia Recent Radiation Research and
Technology Development in Croatia
09:20 A14-02 W. A. P. Calvo Brazil Multipurpose γ-Irradiator and Mobile
Unit with an Electron Beam Accelerator
Developed in Brazil
09:40 A14-03 L. Lanuza Philippines Radiation Processing in the Philippines:
Developments and Prospects
10:00 A14-04 A.Adu-Gyamfi Ghana Radiation Processing in Ghana:
Achievements, Prospects and Challenges
10:20 A14-05 E. F. Prieto MirandaCuba Radiation Processing in Cuba: Past,
Present and Perspective
10:40 A14-06 J. W.Rangel Urrea Mexico Drafting and Preparation of Proposals of
Irradiation Plants: Mexico Experience
Coffee break: 11:00–11:15
B15 09:00–11:00 Advances and Trends in Radiotracer and
Venue: Room M2 Radiation Science and Technology II
Chair: Harish Jagat Pant (India)
TSec: Patrick Brisset (IAEA)
Time Id Presenter
09:00 B15-01 T. Bjørnstad Norway Nuclear-Based Monitoring of Industrial
Mass Flow I: The Potential Use of Small
Transportable Neutron Generators
09:10 B15-02 T. Bjørnstad Norway Nuclear-Based Monitoring of Industrial
Mass Flow II: The Potential Use of Small
Transportable Neutron Generators
09:20 B15-03 R. K.Gupta India Residence Time Distribution
Measurements in Industrial Scale Reactors
with Recycle Using Radiotracer Technique
09:40 B15-04 H.Arahmane Morocco Neutron-γ Discrimination Using
Non-Negative Matrix Factorization Blind
Sources Separation Algorithms
Continued. . .
47
Fri
ICARST–2017 Friday 28 April 2017
B15 continued. . .
Time Id Presenter
10:00 B15-05 Y. Yang China, P. R. Contrabands Detection with a Low
Energy Electron Linac Driven
Photoneutron Source
10:20 B15-06 P. Francus Canada Combining CT Scan and Particle Imaging
Techniques: Developing New
Applications to Sediment Transport
—Discussion—
Coffee break: 11:00–11:15
A15 11:15–13:15 Emerging Radiation Technologies
Venue: Board Room B/M1
Chair:Monique Lacroix (Canada)
TSec: Bum Soo Han (IAEA)
Time Id Presenter
11:15 A15-01 N.Ramamoorthy India Economics of Radiation Processing
Technology: Posers and Prospects
11:35 A15-02 R.Wach Poland Radiation Modification of
Carboxymethylated Chitosan: From
Basics to Applications
11:45 A15-03 D. Staack USA Remediation of Petroleum Impacted Soils
with Electron Beam Irradiation
11:55 A15-04 M.Driscoll USA Electron Beam Pretreatment of
Lignocellulosic Biomass
12:05 A15-05 K.Hemvichian Thailand Radiation-Induced Admicellar
Polymerization of Methyl Methacrylate on
Cassava Starch
12:15 A15-06 B.Doan Viet Nam Preparation and Characteristics of
Reduced Graphene Oxide in
Ethanol/Water Solution by γ-Ray
Irradiation
12:25 A15-07 G.Wu China, P. R. Radiation Induced Oxidation,
Cross-Linking and Grafting of Ultra-High
Molecular Weight Polythylene
—Discussion—
Lunch break: 13:15–14:15
48
Fri
Friday 28 April 2017 ICARST–2017
B16 11:15–13:15 Technical Cooperation Success Stories:
Venue: Room M2 Country Reports
Chair: Joon-Ha Jin (Korea, Rep. of)
TSec: Patrick Brisset (IAEA)
Time Id Presenter
11:15 B16-01 K. M.Rodolfo Angola The Participation of the Technological
National Centre in the Technical
Cooperation Programme Activities
11:35 B16-02 A. S.Abdullahi Nigeria Progress, Problems and Prospects of
Radioisotope Technology in Nigeria
11:55 B16-03 P. Baricholo Zimbabwe Industrial Application of Radioisotopes in
Zimbabwean Industries: A Report on RTD
Experiments in Cement Industry, Radon
Monitoring in Coal and Fly Ash of a Small
Thermal Power Plant and NDT Activities
12:15 B16-04 D.Aquino Philippines Computed Tomography for
Characterizing Industrial Materials
12:35 B16-05 C.Omondi Kenya Measurements of Radiotracer Residence
Time Distribution Using a Flow Rig in
Kenya
—Discussion—
Lunch break: 13:15–14:15
CL 14:15–16:15 Closing Plenary
Venue: Board Room B/M1
Chair: Meera Venkatesh (IAEA)
Time Id Presenter
14:15 CL-01 W. A. P. Calvo Brazil Closing Remarks
14:35 CL-02 X.Coqueret France Closing Remarks II
14:55 CL-03 R.Alami Morocco Closing Remarks III
15:15 CL-04 S. Pillai USA Summary
15:35 CL-05 M.Venkatesh IAEA Closing of the Conference
49
Fri
ICARST–2017 Side Events Mon–Wed
Tuesday April 25:
S01 18:30–19:30 Chinese Mission Side Event
Venue: Room M2
The Chinese Permanent Mission will be holding a side event called “China’s Development
in Radiation Science and Technology” on Tuesday, 25 April from 18:30 to 19:30 in room
RoomM2 , followed by a small reception for approximately 100 people from 19:30 to 21:00
on the first floor of the M–Building.
Wednesday April 26:
S02 18:30–19:30 ISTRA Side Event
Venue: Room M2
There will be the “ISTRA Meeting”, organized by the International Society of Tracers and
Radiation Applications, on Wednesday late afternoon in Room M2 , from 18:30 to 19:30.
(NB: No reception).
50
Side
ICARST–2017
Contents
Introduction 1
Programme Committee 2
Conference Secretariat 5
Exhibits 6
Presentations and Proceedings 9
Abbreviations 10
Floor Plans 11
Timetable 15
Monday 24 April 2017 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16
Tuesday 25 April 2017 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21
Wednesday 26 April 2017 . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27
Thursday 27 April 2017 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 37
Friday 28 April 2017 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47
Side Events Mon–Wed . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50
Abstracts 79
OP: Opening Plenary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 79
OP-04 A. G. Chmielewski,
Ionizing Radiation: Innovative and Effective Tool for Science
and Industry . . . . . . . . . . . . . . . . . . . . . . . . . . . 80
A01: Trends in Radiation Science and Technology . . . . . . . . . . . . . 81
A01-01 P. Ulański,
Radiation Synthesis of Polymer Nanogels for Biomedical
Applications . . . . . . . . . . . . . . . . . . . . . . . . . . . . 82
A01-02 L. Shen,
Status and Prospect of Application of Radiation Science and
Technology in China: A National Report . . . . . . . . . . . 83
A01-03 B. Croonenborghs,
Emerging Areas of Radiation Sterilization . . . . . . . . . . . 84
A01-04 L. V. Abad, et al.,
Radiation-Modified Carrageenan as Plant Food Supplement:
Making a Breakthrough with Philippine Farmers . . . . . . 85
51
ICARST–2017
A01-05 J. Wishart, et al.,
Recent Progress in Pulse Radiolysis Detection Methods and
their Application to Ionic Liquid-Based Systems for Closing
the Nuclear Fuel Cycle . . . . . . . . . . . . . . . . . . . . . . 86
A01-06 P. Vasquez,
Overview of Disinfection of Cultural Heritage Artefacts and
Archive Materials by Ionizing Radiation in Brazil: Culture
Meets Nuclear . . . . . . . . . . . . . . . . . . . . . . . . . . . 87
A02: Advanced Polymeric Materials . . . . . . . . . . . . . . . . . . . . . 88
A02-01 O. Güven,
Past, Present and Near Future of Radiation Processing of
Polymers . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 89
A02-02 X. Coqueret,
Radiation Curing by Cross-Linking Polymerization of Multi-
functional Monomers: A Comparison Between Free Radical
and Cationic Mechanisms . . . . . . . . . . . . . . . . . . . . 90
A02-03 M. Lacroix,
Use of Irradiation, for the Development of Active Edible
Coatings, Beads and Packaging to Assure Food Safety and
to Prolong Preservation . . . . . . . . . . . . . . . . . . . . . 91
A02-04 Z. Ghazali, et al.,
Radiation Grafted Antimicrobial Film for Advanced Active
Packaging Application . . . . . . . . . . . . . . . . . . . . . . 92
A02-05 C. Vasile, et al.,
Radiation Mediated Bioactive Compounds Immobilization
on Polymers to Obtain Multifunctional Food Packaging Ma-
terials . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 93
A02-06 E. Hegazy, et al.,
Radiation Processing of Natural and Synthetic Polymers for
Potential Applications . . . . . . . . . . . . . . . . . . . . . . 94
A03: Advances and Trends in Radiation Science and Technology . . . . . 95
A03-01 M. Zhai, et al.,
Novel Ion Exchange Membranes Synthesized by Radiation
Grafting Technique for Application in Vanadium Redox Bat-
teries . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 96
A03-02 M. Yu, et al.,
Irradiation Induced Modification of Nanoporous Metal Or-
ganic Frameworks . . . . . . . . . . . . . . . . . . . . . . . . 97
A03-03 G. Burillo, et al.,
Synthesis of Amine-Containing Surfaces in Poly(Tetrafluoro-
ethylene) by γ-Radiation . . . . . . . . . . . . . . . . . . . . . 98
52
ICARST–2017
A03-04 Y. Kodama, et al.,
Polycarbonate Chromatography Column to Be Used in a
99Mo/99mTc Generator Irradiated in Saline Solution with
EB and γ-Rays . . . . . . . . . . . . . . . . . . . . . . . . . . . 99
A03-05 M.-C. Dubois-Clochard, et al.,
EB Irradiation on Piezo-PVDF: Beneficial Effect for Harvest-
ing Energy Application . . . . . . . . . . . . . . . . . . . . . 100
A03-06 J. Chen, et al.,
Co-Reduction Synthesis of Graphene/Au Nanocomposite
from Graphene Oxide/Au3` Solution upon γ-Irradiation . . 101
A03-07 N. A. F. Othman, et al.,
An Improved Method of Producing Adsorbent for Metal
Removal Using Radiation Induced Graft Polymerization . . 102
A03-08 V. Luo,
Fabric Modification by Radiation Methods . . . . . . . . . . 103
A04: Radiation for Environmental Protection I . . . . . . . . . . . . . . . 104
A04-01 E. Takács,
Ionizing Radiation Induced Decomposition of Antibiotics in
Waste Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . 105
A04-02 J. Wang, et al.,
Ionizing Irradiation-Induced Degradation of PPCPs in Aque-
ous Solution . . . . . . . . . . . . . . . . . . . . . . . . . . . . 106
A04-03 S. Pillai, et al.,
Efficacy of Electron Beam Irradiation to Address Emerging
Microbial Contaminants in Water Reuse Programmes . . . . 107
A04-04 S. Borrely, et al.,
Toxicity Assays Applications for Assessing Acute Effects for
Radiation Decomposition of Organics in Waters . . . . . . . 108
A04-05 Y. Sun, et al.,
Radiation TechnologyApplication in Environmental Protection109
A05: Advances in Radiation Chemistry Research I . . . . . . . . . . . . . 110
A05-01 L. Wojnárovits,
Basic Radical Reactions in Water Treatment by Ionizing Ra-
diation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 111
A05-02 M. Al-Sheikhly,
Synthesis of Novel Fabrics for Extraction of Uranium from
Seawater . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 112
A05-03 M. Mostafavi,
Ultrafast Electron Transfer Studied by Picosecond Pulse Ra-
diolysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 113
53
ICARST–2017
A05-04 M.-C. Dubois-Clochard,
Advances in Etched Ion-Track Polymer Membranes for Envi-
ronmental and Microelectronic Applications . . . . . . . . . 114
A05-05 S. Goldstein,
Using Ionizing Radiation for Studying Radical Reactions
with Nitroxides: Implications for their Biological Activity . 115
A05-06 J. Barilla, et al.,
Influence of N2O and Ethanol on the Chemical Stage of Ra-
diobiological Mechanism . . . . . . . . . . . . . . . . . . . . 116
A05-07 K. Marzouki, et al.,
EPR Characterization of γ-Irradiated Xerogels . . . . . . . . 117
A06: Dosimetry and Standards for Radiation Processing . . . . . . . . . 118
A06-01 A. Kovács,
Process Control Methods in Radiation Technologies . . . . . 119
A06-02 A. Miller, et al.,
Dosimetry and Process Control for Using Low Energy Elec-
tron Beams for Sterilization or Decontamination of Surfaces 120
A06-03 F. Kuntz, et al.,
Is IQ/OQ/PQ Part of Irradiation Process Control? . . . . . . 121
A06-04 Y. Zhang, et al.,
Dosimetry Standards and Dissemination Systems for Radia-
tion Processing in China . . . . . . . . . . . . . . . . . . . . . 122
A06-05 S. Ebraheem,
EPRDosimetry Systems; Assessment andDeveloped inNCRRT123
A07: Advances in Radiation Chemistry Research II . . . . . . . . . . . . . 124
A07-01 V. Feldman,
The Radiation Chemistry of Organized Systems: Basic Stud-
ies and Implications . . . . . . . . . . . . . . . . . . . . . . . 125
A07-02 M. Jonsson,
Interfacial Radiation Chemistry in Nuclear Technology . . . 126
A07-03 C. I. Horak,
Radiation Sterilization of Devices and Scaffolds for Tissue
Engineering . . . . . . . . . . . . . . . . . . . . . . . . . . . . 127
A07-04 A. W. El Naggar, et al.,
Effect of Sterilization by γ-Irradiation on Biocompatibility
of Starch-Based Polymers and Composites Suitable for Stem
Cell Growth . . . . . . . . . . . . . . . . . . . . . . . . . . . . 128
A07-05 I. P. Kavirayani,
Radiation Chemical Studies Leading to the Development of
Selenium Radioprotectors . . . . . . . . . . . . . . . . . . . . 129
54
ICARST–2017
A07-06 O. Belyakov,
The IAEA Research on Radiation Sterilization in Tissue Bank-
ing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 130
A08: Radiation Sources and Facilities:Panel Discussions . . . . . . . . . . 131
A08-01 P. Dethier,
Review of the Two New Rhodotron Accelerators: The Com-
pact 10MeV TT50 and the High Energy 40MeV Rhodotron . 132
A08-02 R. Wiens,
A Billion Curies and Counting: Ensuring 60Co Supply and
Disposal for Decades to Come . . . . . . . . . . . . . . . . . 133
A08-03 B. Han, et al.,
How to Apply Radiation Technology for Pollution Control . 134
A08-04 A. Bryazgin, et al.,
ILU Industrial Electron Accelerators . . . . . . . . . . . . . . 135
A08-05 W. Peng,
EB Technology vis-a-vis γ-Radiation for Irradiation Steriliza-
tion: Emerging Scenario . . . . . . . . . . . . . . . . . . . . . 136
A08-06 A. K. Kohli,
γ-Irradiator Technology: Challenges and Future Prospects . 137
A09: Preservation of Cultural Heritage . . . . . . . . . . . . . . . . . . . . 138
A09-01 J. Havermans, et al.,
Disinfection and Consolidation of Archived Materials and
Cultural Heritage Artefacts by Radiation Processing Tech-
niques . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 139
A09-02 B. Katušin-Ražem, et al.,
Irradiation Method in the Protection of Cultural Heritage
Objects Endangered by Massive Biodegradation . . . . . . . 140
A09-03 I. V. Moise,
Radiation Processing for Cultural Heritage Preservation: Ro-
manian Experience . . . . . . . . . . . . . . . . . . . . . . . . 141
A09-04 Q.-K. Tran,
Development of New Radiation-Curing Monomers-Resins
Systems for the Consolidation of Wooden Cultural Heritage
Artefacts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 142
A09-05 S. Baccaro, et al.,
Application of Ionizing Radiation for Cultural Heritage . . . 143
A09-06 L. Cortella, et al.,
Uses and Prospects in γ-Biocide Treatments for Cultural
Heritage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 144
55
ICARST–2017
A10: Development in Electron Accelerators Technology . . . . . . . . . . 145
A10-01 Y. Zhang,
Addressing Challenges Posed by Electron Beam Irradiation
through Innovation . . . . . . . . . . . . . . . . . . . . . . . . 146
A10-02 C. Cooper,
Illinois Accelerator Research Center . . . . . . . . . . . . . . 147
A10-03 T. Kroc,
A Compact Superconducting RF Accelerator for Electron
Beam and X-Ray Irradiation . . . . . . . . . . . . . . . . . . . 148
A10-04 F.-H. Roegner, et al.,
Low-Energy Electron Irradiation for Novel Applications in
Medical Production and Pharma . . . . . . . . . . . . . . . . 149
A10-06 N. Kuksanov, et al.,
DC ELV Accelerators: Development and Application . . . . 150
A10-07 A. Weidauer, et al.,
Electron Treatment of Seed . . . . . . . . . . . . . . . . . . . 151
A11: Safety and Security Perspectives of Radiation Facilities . . . . . . . 152
A11-01 M. Frenzel,
Upgrading Safety and Security of γ-Irradiation Facilities:
Possibilities and Limitations . . . . . . . . . . . . . . . . . . . 153
A11-02 F. Schmitz,
Safety Improvements of an Industrial Irradiation Facility . . 154
A11-03 M. Alcerreca,
Upgrading andContinuous Improvement of ININ γ-Irradiation
Facility . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 155
A11-04 M. Mouhib, et al.,
Enhancing Nuclear Security System of Irradiation Facility
SIBO INRA/Tangier Morocco . . . . . . . . . . . . . . . . . . 156
A11-05 G. Yu, et al.,
Development and Application of Electron Linear Accelerator
of CIAE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 157
A12: Radiation for Environmental Protection II . . . . . . . . . . . . . . . 158
A12-01 S. Cabo Verde, et al.,
Virucidal Potential of γ-Radiation . . . . . . . . . . . . . . . 159
A12-02 S. Mezyk,
Removal of Wastewater Pharmaceutical Chemical Contami-
nants Using AOPs . . . . . . . . . . . . . . . . . . . . . . . . 160
A12-03 M.-H. Wu,
Applications of Radiation Technology in Control and Treat-
ment for Environmental Pollution . . . . . . . . . . . . . . . 161
56
ICARST–2017
A12-04 S. M. Cha, et al.,
Application of Mobile Electron Beam for Remediation of
Soil and Groundwater Contaminated with Leachate from
Animal Carcass Burial Sites . . . . . . . . . . . . . . . . . . . 162
A12-05 B. Batchelor, et al.,
Electron Beam Treatment for Potable Water Reuse: Removal
of Bromate and Perfluorooctanoic Acid . . . . . . . . . . . . 163
A12-06 G. Sági, et al.,
Changes in the Biological Degradability and Toxicity of Sul-
fonamide Antibiotics in Activated Sludge and River Water
due to Ionizing Radiation Treatment . . . . . . . . . . . . . . 164
A13: Advanced Nano Materials . . . . . . . . . . . . . . . . . . . . . . . . 165
A13-01 C. Dispenza,
Radiation Synthesis of Nanosized Drug Delivery Devices . . 166
A13-02 M. Grasselli, et al.,
Protein-BasedNanoparticles Prepared by Radiation-Induced
Cross-Linking . . . . . . . . . . . . . . . . . . . . . . . . . . . 167
A13-03 W. Pasanphan, et al.,
Molecular Design and Synthesis of Different Polymer-Based
Nanoparticles as Nanocarriers Using Irradiation Techniques 168
A13-04 K. V. Katti,
Green Nanotechnology in Nuclear Medicine: Tumor Spe-
cific Radioactive Gold Nanoparticles for New Approaches
in Cancer Therapy . . . . . . . . . . . . . . . . . . . . . . . . 169
A13-05 G. H. C. Varca, et al.,
State of the Art and Current Advances on Protein Cross-
Linking by Irradiation: Protein BasedNanocarriers andBioac-
tive Nanoparticles . . . . . . . . . . . . . . . . . . . . . . . . 170
A13-06 Y. Bondar, et al.,
Radiation-Chemical Synthesis ofNanocompositeAdsorbents
Based onPolypropylene Fibres for Selective Removal ofHeavy
Metals and Radionuclides . . . . . . . . . . . . . . . . . . . . 171
A13-07 A. Salih, et al.,
Preparation of Polyurethane Acrylate/ OrganicallyModified
Montmorillonite Nanocomposites by Electron Beam Radia-
tion Curing . . . . . . . . . . . . . . . . . . . . . . . . . . . . 172
A14: Technical Cooperation Success Stories . . . . . . . . . . . . . . . . . 173
A14-01 B. Mihaljević,
Recent Radiation Research and Technology Development in
Croatia . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 174
57
ICARST–2017
A14-02 W. A. P. Calvo, et al.,
Multipurpose γ-Irradiator and Mobile Unit with an Electron
Beam Accelerator Developed in Brazil . . . . . . . . . . . . . 175
A14-03 L. Lanuza, et al.,
Radiation Processing in the Philippines: Developments and
Prospects . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 176
A14-04 A. Adu-Gyamfi,
Radiation Processing in Ghana: Achievements, Prospects
and Challenges . . . . . . . . . . . . . . . . . . . . . . . . . . 177
A14-05 E. F. Prieto Miranda,
Radiation Processing in Cuba: Past, Present and Perspective 178
A14-06 J. W. Rangel Urrea, et al.,
Drafting and Preparation of Proposals of Irradiation Plants:
Mexico Experience . . . . . . . . . . . . . . . . . . . . . . . . 179
A15: Emerging Radiation Technologies . . . . . . . . . . . . . . . . . . . 180
A15-01 N. Ramamoorthy,
Economics of Radiation Processing Technology: Posers and
Prospects . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 181
A15-02 R. Wach, et al.,
RadiationModification ofCarboxymethylatedChitosan: From
Basics to Applications . . . . . . . . . . . . . . . . . . . . . . 182
A15-03 J. Lassalle, et al.,
Remediation of Petroleum Impacted Soilswith ElectronBeam
Irradiation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 183
A15-04 M. Driscoll, et al.,
Electron Beam Pretreatment of Lignocellulosic Biomass . . . 184
A15-05 K. Hemvichian, et al.,
Radiation-Induced Admicellar Polymerization of Methyl
Methacrylate on Cassava Starch . . . . . . . . . . . . . . . . 185
A15-06 B. Doan, et al.,
Preparation and Characteristics of Reduced Graphene Oxide
in Ethanol/Water Solution by γ-Ray Irradiation . . . . . . . 186
A15-07 G. Wu, et al.,
Radiation Induced Oxidation, Cross-Linking and Grafting
of Ultra-High Molecular Weight Polythylene . . . . . . . . . 187
B01: Advances and Trends in Radiotracer and Radiation Science and
Technology I . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 188
B01-01 Q. Nguyen Huu, et al.,
Improved Procedures for Preparation of Argon-41 Gaseous
Radiotracer from Solid Clathrate Compound . . . . . . . . . 189
58
ICARST–2017
B01-02 L. Kalo, et al.,
Experimental Study ofConical FluidizedBedUsingRadioiso-
tope Based Technique . . . . . . . . . . . . . . . . . . . . . . 190
B01-03 J. Phirani, et al.,
Predicting Dead Pore-Volume of Pores in a Porous Media
from Single Tracer Experiment . . . . . . . . . . . . . . . . . 191
B01-04 S. Roy, et al.,
Application of RPT and Densitometry for Measuring Liquid
Velocity Field and Void Fraction in Convective Boiling Flows 192
B01-05 C. H. de Mesquita, et al.,
Holdup Analysis of a Bubble Column Using an Industrial
Fourth Generation Like γ-Ray Tomography . . . . . . . . . . 193
B02: Education, Training and Safety . . . . . . . . . . . . . . . . . . . . . 194
B02-01 O. Potier,
A New Approach to Teach Beginners How to Analyze Trac-
ing Results by a Rapid Visual Method . . . . . . . . . . . . . 195
B02-02 P. Livolsi,
Education Training: INSTN Designated as an IAEA Collabo-
rating Centre . . . . . . . . . . . . . . . . . . . . . . . . . . . 196
B02-03 P. Brisset, et al.,
Training andCertification in Radiotracers and Sealed Sources
Industrial Applications . . . . . . . . . . . . . . . . . . . . . 197
B02-04 D. Telleria,
The IAEA Methodology for Radiological Protection of the
Environment, Including Human and Non-Human Biota . . 198
B02-05 A. Mahjoub, et al.,
Radiation Sciences and Applications Programme in Arab
Countries . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 199
B02-06 S. A. Masinza,
Quality Management in Radiotracer Technology and Sealed
Source Applications . . . . . . . . . . . . . . . . . . . . . . . 200
B03: Radiotracers for Industrial Processes Optimization and Safety I . . . 201
B03-01 R. Alami,
Study by Radiotracer of a Phosphoric Acid Production Line 202
B03-02 V. Yelgaonkar, et al.,
Studying Flow Dynamics of Catalyst Powder in CCU for
Troubleshooting . . . . . . . . . . . . . . . . . . . . . . . . . . 203
B03-03 H. A. Affum, et al.,
The Application of CFD for Modelling Flow and Visualiza-
tion in a Cement Mill and Experimental RTD Validation
Using Radiotracer Technology . . . . . . . . . . . . . . . . . 204
59
ICARST–2017
B03-04 H. Ben Abdelouahed, et al.,
Radiotracers for Pulp Flow Dynamics Study in Three Differ-
ent Phosphoric Acid Reactors . . . . . . . . . . . . . . . . . . 205
B03-05 S. Sugiharto,
Residence Time Distribution Study of Geothermal Vapour
Flow in Pipe Using Axial Dispersion Modelling . . . . . . . 206
B03-06 M. Sarkar, et al.,
Radiotracer Investigation of a Pulp and Paper Mill Effluent
Treatment Plant . . . . . . . . . . . . . . . . . . . . . . . . . . 207
B04: Mitigating Climate Change: Protecting Coast Line and Environment 208
B04-01 C. Hughes,
Radiotracer Methods for Understanding Contaminant Dy-
namics in Aquatic Environments . . . . . . . . . . . . . . . . 209
B04-02 D. Pham Van Bang,
Nuclear TechnologiesApplied to Sediment Transport in River,
Estuarine and Coastal Zones to Validate CFD Codes . . . . . 210
B04-03 K. Bhar, et al.,
Radiotracer Study to Investigate the Spatial Dispersion Pat-
tern of Dredged Materials in Hooghly Estuary, West Bengal,
India . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 211
B04-04 J. Vianna Bandeira, et al.,
Technetium-99m: From Nuclear Medicine Applications to
Fine Sediment Transport Studies . . . . . . . . . . . . . . . . 212
B04-05 P. Terrier, et al.,
The Use of Nucleonic Gauge JTTX in the Port of Nantes Saint-
Nazaire . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 213
B04-06 R. Suárez-Antola,
Water Renewal in Montevideo’s Bay II: A Compartmental
Fractional Model for Tritium Kinetics . . . . . . . . . . . . . 214
B04-07 A. Ioannidou, et al.,
The Radiotracer 7Be in Studying Environmental Processes . 215
B05: Radiotracers for Energy of the Future I . . . . . . . . . . . . . . . . . 216
B05-01 A. Toukan, et al.,
Liquid Holdup Studies in a Co-current Gas-Liquid Upflow
Moving Packed Bed Reactor with Porous Catalyst Using γ-
Ray Densitometry . . . . . . . . . . . . . . . . . . . . . . . . 217
B05-02 V. Alexander, et al.,
Bed Expansion Studies in Upflow Moving Catalytic Packed/
Expanded Bed Hydrotreating Reactor Using γ-Ray Densito-
metry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 218
60
ICARST–2017
B05-03 M. Sheoran, et al.,
Radioactive Tracing of an Industrial Scale Continuous Pulp
Digester . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 219
B05-04 D. Aquino, et al.,
Evaluating the Operating Conditions of a Rectifier Column
Using γ-Column Scanning . . . . . . . . . . . . . . . . . . . . 220
B05-05 Q. Nguyen Huu, et al.,
γ-Scanning Technique as an Efficient Investigation Tool for
Diagnostics and Troubleshooting in Industry: Case Studies . 221
B05-06 C. P. K. Dagadu,
Validation of CFD Codes Using Radiotracer RTD Analysis
of Stirred Vessels . . . . . . . . . . . . . . . . . . . . . . . . . 222
B06: Radiation Techniques for Energy of the Future . . . . . . . . . . . . 223
B06-01 M. Derivet, et al.,
The γ-Scanner: A Tool for the Quality Control of the Process
of Alcohol Distillation . . . . . . . . . . . . . . . . . . . . . . 224
B06-02 T. Abd El Slam,
A New Method for Detecting Trace Oil Concentration by
Neutron Radiography Technique . . . . . . . . . . . . . . . . 225
B06-03 C. Sebastian Calvo,
Leaks Determinations in Reboilers fromNatural Liquid Frac-
tioning Units . . . . . . . . . . . . . . . . . . . . . . . . . . . 226
B06-04 L. Sabri, et al.,
RPT for Tracking Microalgae Cell Movement in Split Photo-
bioreactor Column . . . . . . . . . . . . . . . . . . . . . . . . 227
B06-05 A. Toukan, et al.,
Flow Regime Identification in a Co-Current Gas-Liquid Up-
flow Moving Packed Beds Reactor Using γ-Ray Densitometry228
B07: Radiotracers for Energy of the Future II . . . . . . . . . . . . . . . . 229
B07-01 Z. Idiri, et al.,
Simulation and Optimization of a Neutron Backscattering
Analysis Set-Up Using MCNP5 Code . . . . . . . . . . . . . 230
B07-02 S.-H. Jung, et al.,
RPT Study on a Vertical Impeller Mixer . . . . . . . . . . . . 231
B07-03 A. Sultan, et al.,
Linear Attenuation Coefficients and Gas Holdup Distribu-
tions of Bubble Column with Vertical Internal Bundle for FT
Synthesis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 232
B07-04 A. Ouardi, et al.,
Numerical Simulation of Measurement by γ-Ray Scanning
of Coke Deposition in Packed Bad of Distillation Column . . 233
61
ICARST–2017
B07-05 S. Roy, et al.,
Noninvasive Radiation Based Densitometry and Velocimet-
ric Monitoring of Fluidization of Coal and Bottom Ash Mix-
tures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 234
B07-06 V. Khane, et al.,
Experimental Study of Pebble Flow Dynamics in a PBMR
Using RPT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 235
B08: Seeing the Invisible: Structure Imaging—Safe and Effective Industry I236
B08-01 N. G. Cutmore, et al.,
Next-Generation Fast-Neutron/X-Ray Scanner for Air Cargo
Interrogation . . . . . . . . . . . . . . . . . . . . . . . . . . . 237
B08-02 H. Ben Abdelouahed, et al.,
Monte Carlo Simulation and Experimental Verification of
Blockages in Pipelines Using γ-Ray Computed Tomography 238
B08-03 X. Zhao, et al.,
Associated Image Processing Algorithm in Dual-Projection
Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 239
B08-04 K. N. Myaing,
Comparison of Image Reconstructions for γ-Transmission
Computed Tomography System by Using MATLAB and i-
Gorbit Software . . . . . . . . . . . . . . . . . . . . . . . . . . 240
B08-05 T. D. Dang Nguyen, et al.,
Gorbit – The Flexible γ-Computed Tomography System for
Pipeline Inspection . . . . . . . . . . . . . . . . . . . . . . . . 241
B09: Radiotracer for Managing Natural Resources . . . . . . . . . . . . . 242
B09-01 S. Mimount, et al.,
Development of Radiometric Methods for Optimization of
Phosphate Transport Process by “Slurry Pipe” . . . . . . . . 243
B09-02 F. Diaz, et al.,
Determination of Mineral Behaviour in Ball Mills at Chilean
Copper Minning Using Radioactive Tracers . . . . . . . . . . 244
B09-03 M. Rogowski, et al.,
Radiotracer Methods for Ore and Flotation Tailings Leaching 245
B09-04 H. J. Pant, et al.,
Radiotracer Investigation in an Industrial-Scale Fluid Cat-
alytic Cracking Unit . . . . . . . . . . . . . . . . . . . . . . . 246
B09-05 J. Tickner, et al.,
Developing a Commercial Facility for Rapid Assay of Gold
and other Elements in Mineral Ores Using γ-Activation
Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 247
62
ICARST–2017
B09-06 R. M. Moreira,
A Tracer Application in Detecting Damage to Oil Industry
Piping . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 248
B10: Radiotracers for New Materials Development . . . . . . . . . . . . . 249
B10-01 H. Makil, et al.,
Quality Control of Neutron-Absorber Materials for the Nu-
clear Fuel Cycle: Principle of the JEN_3 Neutron Backscat-
tering Gauge . . . . . . . . . . . . . . . . . . . . . . . . . . . 250
B10-02 A. Kleinrahm,
Radionuclide Technique in Mechanical Engineering: A Pow-
erful Measuring Method for Tribological Tasks — Installa-
tions at and Services of ZAG Zyklotron AG . . . . . . . . . . 251
B10-03 B. Artemiev, et al.,
Replacing the Isotopic Radiation Sources in Thickness Mea-
surement on X-Ray . . . . . . . . . . . . . . . . . . . . . . . . 252
B10-04 F. Ditrói, et al.,
Development of Thin Layer Activation for Wear Measurement253
B10-05 F. Genezini, et al.,
Industrial Applications of the IEA-R1 Research Reactor in
Brazil . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 254
B11: Seeing the Invisible: Structure Imaging—Safe and Effective Industry II255
B11-01 G. Ud Din, et al.,
Investigation of Two-Phase Flow Behaviour Across a 90 De-
gree Horizontal Bend: CFD Simulation and γ-Computer
Tomography Validation . . . . . . . . . . . . . . . . . . . . . 256
B11-02 J.-H. Jin, et al.,
New Developments on the Automatic γ-Column Scanner . . 257
B11-03 H. J. Pant,
Radiotracer Applications in Industry and Environment . . . 258
B11-04 G. A. Johansen, et al.,
Tomographic Methods for Multiphase Flow Measurement . 259
B11-05 G. Maghella, et al.,
Determination of Interfaces in Packed Columns by Using
Sealed Sources . . . . . . . . . . . . . . . . . . . . . . . . . . 260
B11-06 A. Saadaoui, et al.,
A γ-Ray Computed Tomography for Investigating the Wood
Structure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 261
63
ICARST–2017
B12: Radiation Techniques for Industrial Processes Optimization and
Safety II . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 262
B12-01 J. Thereska, et al.,
Radiotracer Residence-Time Distribution Method in Diag-
nosing Industrial Processing Units: Case Studies . . . . . . . 263
B12-02 J. S. Rawat, et al.,
Investigation of the Multiple Side Injections on Hydrody-
namics of the Gas-Solids Fluidized Bed Using Radiotracer
Based Techniques . . . . . . . . . . . . . . . . . . . . . . . . . 264
B12-03 G. Ud Din,
Radiotracer and Sealed Source Technologies for Measure-
ments in Industry . . . . . . . . . . . . . . . . . . . . . . . . . 265
B12-04 K. El Korchi, et al.,
Radioisotope Techniques for Detection of Coking in Liquid
Flow through a Solid Phase in a Lab-ScaleDistillationColumn’s266
B12-05 S. Goswami, et al.,
Measurement of Residence Time Distribution of Wastewater
in a ConstructedWetland System Using Radiotracer Technique267
B12-06 S. Y. Adzaklo, et al.,
Radiotracer Investigation of the Effect of Impeller Type on
Mixing in Industrial Process Simulator . . . . . . . . . . . . 268
B13: Radiotracer for Managing of Natural Resources, Energy and Processes269
B13-01 T. B. O. Jentsch,
Investigation of Heavy Metal Release at a Municipal Solid
Waste Incineration Facility: An Excellent Example for the
Unique Potential of Intrinsic Radiotracer Application to the
Investigation of Industrial Processes in Chemical Engineering270
B13-02 J. Abdullah, et al.,
Radiotracer Investigation in an Aeration Tank of a Waste
Water Treatment Plant . . . . . . . . . . . . . . . . . . . . . . 271
B13-03 F. Z. Oujebbour, et al.,
Data Fusion Approach for Improving the Reliability of Ra-
diographic Testing and other ComplementaryNDT Techniques272
B13-04 I. I. Mumuni, et al.,
Neutron Backscatter Technique as an Alternative Method for
Quality Assurance and Standardization of Petroleum Products273
B13-05 M. P. Hlaing, et al.,
Identification of the Internal Condition of Crude Oil Distilla-
tion Unit Using γ-Column Scanning Technique in Myanmar 274
64
ICARST–2017
B14: Radiation for Cultural Heritage Characterization . . . . . . . . . . . 275
B14-01 J. L. Boutaine,
A Survey of the Possibilities of Various Radiographic Tech-
niques for the Non Destructive Examination of Cultural Her-
itage Artefacts . . . . . . . . . . . . . . . . . . . . . . . . . . . 276
B14-02 M. J. G. Gichuru, et al.,
Application of Ionizing radiation in Studying Akaba and
Masai Art Objects Made from Glass . . . . . . . . . . . . . . 277
B14-03 Ş. Ekinci,
Radiographic Investigation of Archaeological Objects . . . . 278
B14-04 B. Artemiev, et al.,
Using X-Rays to Detect Hidden Images (Old Masters) on
Priming Canvases . . . . . . . . . . . . . . . . . . . . . . . . . 279
B14-05 R. Outayad, et al.,
Some Applications of X-Rays in the Service of the Archaeo-
logical Site of Volubilis . . . . . . . . . . . . . . . . . . . . . . 280
B14-06 F. De Beer,
Secrets and Mysteries of our Past Revealed by Neutron and
X-Ray Radiography/Tomography . . . . . . . . . . . . . . . 281
B14-07 A. Bensitel, et al.,
The Radiography in the Service of the Preservation of the
Moroccan Historical Heritage . . . . . . . . . . . . . . . . . . 282
B15: Advances and Trends in Radiotracer and Radiation Science and
Technology II . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 283
B15-01 T. Bjørnstad,
Nuclear-Based Monitoring of Industrial Mass Flow I: The
Potential Use of Small Transportable Neutron Generators . . 284
B15-02 T. Bjørnstad,
Nuclear-Based Monitoring of Industrial Mass Flow II: The
Potential Use of Small Transportable Neutron Generators . . 285
B15-03 A. Datta, et al.,
Residence Time Distribution Measurements in Industrial
Scale Reactors with Recycle Using Radiotracer Technique . . 286
B15-04 H. Arahmane, et al.,
Neutron-γ Discrimination Using Non-Negative Matrix Fac-
torization Blind Sources Separation Algorithms . . . . . . . 287
B15-05 Y. Yang,
Contrabands Detection with a Low Energy Electron Linac
Driven Photoneutron Source . . . . . . . . . . . . . . . . . . 288
B15-06 P. Francus,
Combining CT Scan and Particle Imaging Techniques: De-
veloping New Applications to Sediment Transport . . . . . . 289
65
ICARST–2017
B16: Technical Cooperation Success Stories: Country Reports . . . . . . . 290
B16-01 K. M. Rodolfo,
The Participation of the Technological National Centre in the
Technical Cooperation Programme Activities . . . . . . . . . 291
B16-02 A. S. Abdullahi,
Progress, Problems and Prospects of Radioisotope Technol-
ogy in Nigeria . . . . . . . . . . . . . . . . . . . . . . . . . . . 292
B16-03 P. Baricholo, et al.,
Industrial Application of Radioisotopes in Zimbabwean In-
dustries: A Report on RTD Experiments in Cement Industry,
Radon Monitoring in Coal and Fly Ash of a Small Thermal
Power Plant and NDT Activities . . . . . . . . . . . . . . . . 293
B16-04 J. Mallillin, et al.,
Computed Tomography for Characterizing IndustrialMaterials294
B16-05 C. Omondi, et al.,
Measurements of Radiotracer Residence Time Distribution
Using a Flow Rig in Kenya . . . . . . . . . . . . . . . . . . . . 295
PA1: Posters PA1: Irradiation Facilities and their Applications . . . . . . 296
PA1-01 A. Abaza,
New Trends in Radiation Dosimeters . . . . . . . . . . . . . 297
PA1-02 S. Abdelgawad,
Setting up of New Radiation Facilities in Alexandria, Egypt 298
PA1-03 J. Abdullah, et al.,
In Situ and Non-Destructive Detection of Oleoresin in Stand-
ingAgarwoodTreesUsing Portable γ-RayTomography Imag-
ing System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 299
PA1-04 A. Adjerad,
Facilitating Sustainable Education in Nuclear Science and
Technology . . . . . . . . . . . . . . . . . . . . . . . . . . . . 300
PA1-05 M. Aljohani, et al.,
Pilot-Scale Study of the Radiation-Induced Silica Removal
from Underground Brackish Water in Saudi Arabia . . . . . 301
PA1-06 S. Baccaro, et al.,
Radiation Activities at ENEA Calliope γ-Facility . . . . . . . 302
PA1-07 H. Bai, et al.,
Detoxification ofHighToxicity Substances byRadiation Trans-
formation Technique . . . . . . . . . . . . . . . . . . . . . . . 303
PA1-08 K. Bergaoui, et al.,
Evaluation of Radiation Shield Integrity of DDNeutron Gen-
erator Facilities by Monte Carlo and Experimental Methods 304
66
ICARST–2017
PA1-09 R. Betesho Babrud, et al.,
Fungal Decontamination of Historical Oil Painting by Using
γ-Ray . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 305
PA1-10 R. Betesho Babrud, et al.,
The Study of γ-Ray Efficiency in Converting Tehran Munici-
pal Sewage Sludge into a Sanitary Fertilizer . . . . . . . . . . 306
PA1-11 C. A. D. Carvalho Filho, et al.,
The Application of Radiochemical and Isotopic Studies to
Inform on the Impact of Acidic Effluent Discharges from the
Caldas Uranium Mine into Neighboring Surface Waters . . 307
PA1-12 D. Chmielewska-Śmietanko, et al.,
Application of Electron Beam for Preservation Biodeterio-
rated Cultural Heritage Paper-Based Objects . . . . . . . . . 308
PA1-13 L. Coretchi, et al.,
Using of Radiation Sterilization . . . . . . . . . . . . . . . . . 309
PA1-14 M. L. Costa, et al.,
Relevant Safety Aspects for Radioactive Tracers in Industrial
Process . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 310
PA1-15 F. Djouider, et al.,
Radiation InducedEnvironmental Remediation of Toxic Cr(VI)
Heavy Metal in Aerated Neutral Solution under Simulated
Industrial Effluent . . . . . . . . . . . . . . . . . . . . . . . . 311
PA1-16 A. Docters, et al.,
Intergrating Management Systems to Good Irradiation Prac-
tices within a Framework of Social Responsibility . . . . . . 312
PA1-17 S. E. Eid,
ESR Dosimetric Properties of Sodium Glutamate . . . . . . . 313
PA1-18 R. El-Motaium,
Ionizing Radiation as a New Technique for Treating Sewage
Wastewater and Sludge in Arid Regions . . . . . . . . . . . . 314
PA1-19 K. Farah, et al.,
EPR Characterization of a Medical Grade Polyethylene for
High Dose Dosimetry . . . . . . . . . . . . . . . . . . . . . . 315
PA1-20 M. Fulop, et al.,
Treatment of Organic Pollutants Based on PCB in the River
Sediment by Electron Beam . . . . . . . . . . . . . . . . . . . 316
PA1-21 E. Furuta, et al.,
A New Fluorescence Detection Method with Plastic Scintil-
lators Using a Conventional LSC-Organic Waste Less Method317
PA1-22 F. Gao,
Optimal Design of 60Co Single Source Radiation Facilitywith
Monte Carlo Method . . . . . . . . . . . . . . . . . . . . . . . 318
67
ICARST–2017
PA1-23 J. R. George, et al.,
Conceptual Development of an Irradiator for Cross-Linking
of Cables Using 60Co γ-Rays . . . . . . . . . . . . . . . . . . 319
PA1-24 R. Gomes, et al.,
Assessment of Safety Systems Design of Industrial Irradia-
tion Facilities in Brazil . . . . . . . . . . . . . . . . . . . . . . 320
PA1-25 S. Goswami, et al.,
Measurement of Residence Time Distribution of Wastewater
in a Constructed Wetland System Using Radiotracer Technique321
PA1-26 U. Gryczka, et al.,
Application of Low Energy Electron Beam inMicrobiological
Decontamination Process . . . . . . . . . . . . . . . . . . . . 322
PA1-27 A. Ihsan, et al.,
Core Neutronic and Source Strength Analyses of 60Co Pro-
duction in Local Power Reactors . . . . . . . . . . . . . . . . 323
PA1-28 B. S. Jang, et al.,
RI-Biomics Technology for the Advance Radioisotope Appli-
cation in Modern Life . . . . . . . . . . . . . . . . . . . . . . 324
PA1-29 C.-H. Jung, et al.,
Effect of γ-Ray and Electron Beam Irradiation on Reduction
of Graphene Oxide Suspension in Aqueous Alcoholic Solution325
PA1-30 W.-G. Kang, et al.,
Radiation Shielding Analyses of a 10MeV LINAC for Elec-
tron Beam and X-Ray at KACST . . . . . . . . . . . . . . . . . 326
PA1-31 Y. Karakirova, et al.,
Optimizing the Size and Composition of Solid State/EPR
Dosimeters . . . . . . . . . . . . . . . . . . . . . . . . . . . . 327
PA1-32 H. Y. Kim, et al.,
Degradation Characteristics and Transformation Products
of Iodinated Contrast Media Using Ionizing Radiation . . . 328
PA1-33 S. Ladjouzi, et al.,
Structural Characterization of γ Irradiated GdBO3/Silica
Composite Obtained by Sol Gel Process . . . . . . . . . . . . 329
PA1-34 K. K. Lay,
Research on Conversion of Natural Wastes to Useful Prod-
ucts by Application of Radiation Processing for Agricultural
Sector of Myanmar . . . . . . . . . . . . . . . . . . . . . . . . 330
PA1-35 G. Liu, et al.,
Dose Increase System in a γ-Irradiator . . . . . . . . . . . . . 331
PA1-36 K. Y. Lwin, et al.,
Human Resource Development for the Application of Ra-
dioisotope Techniques to Industry in Myanmar . . . . . . . 332
68
ICARST–2017
PA1-37 J. Madureira, et al.,
Application of Ionizing Radiation for Treatment and Val-
orization of Cork Wasterwater . . . . . . . . . . . . . . . . . 333
PA1-38 B. Mihaljević, et al.,
Detoxification of Aflatoxin B1 andOchratoxin A by γ-Radiation334
PA1-39 S. Mimount, et al.,
Dosimetric Evaluation in Industrial Gammagraphy Operations335
PA1-40 W. Mohamed Moustafa,
Application of Isotopic TechniquesUsingMathematicalMod-
els in Environmental Process . . . . . . . . . . . . . . . . . . 336
PA1-41 V. Morgunov,
The Numerical Simulation of Cultural Heritage Radiation
Treatment by Monte Carlo Method . . . . . . . . . . . . . . . 337
PA1-42 M. Mouhib, et al.,
Upgrading of 60Co in Temporary Pool for Dry Storage Irra-
diation Facility SIBO INRA/Tangier Morocco . . . . . . . . 338
PA1-43 M. Mouhib,
Enhancing Safety and Control Features of Radiation Process-
ing Facility SIBO INRA/Tangier Morocco . . . . . . . . . . . 339
PA1-44 L. Ounalli Mejri, et al.,
The Efficiency of Radiation Processing by the Tunisian 60Co
Industrial Irradiator after 16 Years of Use . . . . . . . . . . . 340
PA1-45 H. J. Pant, et al.,
Measurement of Voidage/Holdup in Industrial Process Sys-
tems Using γ-Ray Densitometry . . . . . . . . . . . . . . . . 341
PA1-46 E. F. Prieto Miranda, et al.,
Dosimetric Characterization of the ISOGAMMA LLoCo Ir-
radiator . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 342
PA1-47 I. Pucić, et al.,
γ-Irradiation in Protection of Cultural Heritage: Effects on
Model Cellulose Based Textiles . . . . . . . . . . . . . . . . . 343
PA1-48 D. Razem, et al.,
Dosimetric Calibration of a Panoramic 60Co γ-Ray Source . 344
PA1-49 M. Rushdi, et al.,
EPR Dosimetric Potential of Ammonium Oxalate Monohy-
drate in Radiation Technology . . . . . . . . . . . . . . . . . 345
PA1-50 F. Salgado,
Development of a Digital Model for the Dosimetry of the
60Co Irradiator at the National Polytechnic School of Ecuador346
PA1-51 M. Šegvić Klarić, et al.,
γ-Irradiation for Cultural Heritage: Treatment of Selected
Fungi on Linen Textile . . . . . . . . . . . . . . . . . . . . . . 347
69
ICARST–2017
PA1-52 B. R. Shah, et al.,
Personal Radiation Dosimetry at Radiological Facilities, Nepal348
PA1-53 Y.-S. Son, et al.,
Electron Beam Techniques for Air Pollution Control . . . . . 349
PA1-54 D. Souza, et al.,
Dosimetric Properties of MgB4O7:Ce and MgB4O7:Ce, Li for
Thermoluminescence Dosimetry Applications . . . . . . . . 350
PA1-55 A. Tegze, et al.,
Radiolysis Induced Degradation of Fluoroquinolones . . . . 351
PA1-56 M. H. Trabelsi, et al.,
Tunisian Experience Assessment of Installing a Pilot 60Co
Source for Irradiation . . . . . . . . . . . . . . . . . . . . . . 352
PA1-57 A. Tripathi, et al.,
γ-Radiation-Co-Cryogelation Induced Synthesis of Macrop-
orous rpCryogels for Bioengineering Applications . . . . . . 353
PA1-58 P. Vasquez, et al.,
Kinetics of Free Radicals Decay Reactions in Cellulosic-Based
Heritage Materials Disinfected by γ-Radiation . . . . . . . . 354
PA1-59 M. V. Vogt, et al.,
Feasibility of Using Irradiation to Degrade a Toxic Dye Com-
pound . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 355
PA1-60 A. Weidauer, et al.,
Toroidal Electron Source . . . . . . . . . . . . . . . . . . . . . 356
PA1-61 A. Zaouak, et al.,
γ-Radiation Induced Decolouration and Degradation on
Aqueous Solutions of Indigo Carmine Dye . . . . . . . . . . 357
PA1-62 Z. Zimek, et al.,
Electron Accelerator for R&D Study and Radiation Processing358
PA2: Posters PA2: Radiation Creation of Materials from Fundamentals to
Application . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 359
PA2-01 S. Abdelrehim,
Developing a Simple Method Using Ionizing Radiation to
Produce Polyacrylic Acid Based Nanoparticles . . . . . . . . 360
PA2-02 Y. Aguilera-Corrales,
Synthesis by γ-Radiation and Characterization of Poly(Vinyl-
pyrrolidone) Nanogel . . . . . . . . . . . . . . . . . . . . . . 361
PA2-03 J. Aktar, et al.,
Application of γ Radiation and Physicochemical Treatment
to Improve the Bioactive Properties of Chitosan Extracted
from Shrimp Shell . . . . . . . . . . . . . . . . . . . . . . . . 362
PA2-04 M. C. Anessi, et al.,
Predicting the Behaviour of a Biomaterial as Bone Replacement363
70
ICARST–2017
PA2-05 I. C. Calina, et al.,
Electron Beam Synthesis of Inulin Hydrogels Extracted from
Helianthus Tuberosus L. . . . . . . . . . . . . . . . . . . . . . . 364
PA2-06 J. Cardoso, et al.,
Recycled HDPE/Vulcanized EPDMMixtures Obtained by
Irradiation Processes . . . . . . . . . . . . . . . . . . . . . . . 365
PA2-07 K. R. C. De Silva, et al.,
Determination of the Radiation Dose Required to Obtain
Desired Viscosity Average Molecular Mass Using Commer-
cially Available Chitosan and Signification of this Technique
in its Applications . . . . . . . . . . . . . . . . . . . . . . . . 366
PA2-08 E. Eisawy,
The Effect of Radiation Environment on Electrical Insulation
Materials . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 367
PA2-09 N. El-Sawy, et al.,
Radiation Synthesis of Acrylic Acid onto Poly(tetrafluoro-
ethylene-perfluorovinyl ether) Film: Chemical Modifications
and Electrical Conductivity . . . . . . . . . . . . . . . . . . . 368
PA2-10 N. Farahat, et al.,
Sorption of Iodine on Ion Exchange Resins . . . . . . . . . . 369
PA2-11 L. M. Ferreira, et al.,
Distinct Polymeric BasedMaterials Prepared/Functionalized
by γ-Irradiation for Biomedical Applications and RomanMo-
saics Preservation . . . . . . . . . . . . . . . . . . . . . . . . . 370
PA2-12 L. Garcia-Uriostegui, et al.,
Synthesis of Cross-Linking Films Based of 3-(Trimethoxysilyl)
Propyl Methacrylate Silanized Xanthan Gum/Lignin and
their Cross-Linking by γ-Radiation, to Potential Application
and Films Packing . . . . . . . . . . . . . . . . . . . . . . . . 372
PA2-13 X. W. Ge,
Monodispersed Polypyrrole Nanoparticles Prepared via Wa-
ter Padiolysis and their Photothermal Therapy on Cancer
Cells . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 373
PA2-14 A. Geraldo, et al.,
Obtention and Characterization of γ-Irradiated Recycled
HDPE/EPDDM Blends . . . . . . . . . . . . . . . . . . . . . 374
PA2-15 S. Ismail, et al.,
γ-Radiation Enhancement of Photocatalytic Activity of Con-
ducting Polyaniline-TiO2 Nanocomposites for Degradation
of Methyl Orange Dye under Visible Light Irradiation . . . . 375
PA2-16 T. Jurkin, et al.,
Radiolytical Synthesis and Mechanism of Gold Nanoparticle
Formation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 376
71
ICARST–2017
PA2-17 M. Kaci,
Functional Properties and Ecotoxicity of Bionanocomposites
Based on PHBV/PLA Blend under Electron Beam Irradiation377
PA2-18 I. U. Khan, et al.,
Studying the Biological Efficacy of Radiation-Treated Ra-
diolabelled DOTA-Bombesin-Decorated Nanoconstructs as
Potential Nanosized Drug Delivery Systems . . . . . . . . . 378
PA2-19 H. B. Kim, et al.,
Fabrication of Advanced Soft Magnetic Nanomaterials Using
the Radiation . . . . . . . . . . . . . . . . . . . . . . . . . . . 379
PA2-20 M. Klingbeil, et al.,
Development of Advanced Scaffolds and Polymeric Systems
for Improved Cell and Tissue Growth . . . . . . . . . . . . . 380
PA2-21 J. Krstić, et al.,
Mechanical Characteristics and Antibacterial Properties of
Ag-Poly(Vinyl Alcohol)/ws-Chitosan Hydrogel Nanocom-
posites Synthesized by γ-Irradiation Combined with Freeze/
Thaw Cycles . . . . . . . . . . . . . . . . . . . . . . . . . . . . 381
PA2-22 J. Li, et al.,
Dyestuff Free: Colouring Fabrics by Graft Polymerization . . 382
PA2-23 D. Lucan,
Influence of the Coolant Chemistry on the Structural Materi-
als Surfaces Exposed into the Candu NPP Primary Circuit . 383
PA2-24 E.-M. Lungulescu, et al.,
Radiation-InducedOxidation in γ-IrradiatedUHMWPEMod-
ified with Hydroxyapatite . . . . . . . . . . . . . . . . . . . . 384
PA2-25 J. Madrid, et al.,
Optimization of Electron Beam-Induced Synthesis of Poly-
propylene-g-poly(GlycidylMethacrylate) for Cr(VI) andCd(II)
Adsorption Using Full Factorial Design . . . . . . . . . . . . 385
PA2-26 G. Mahmoud, et al.,
Radiation Development of (Polyvinyl Pyrrolidon/Acrylic
Acid)- Silver Nanocomposite for the Disposal of Phenolic
Compounds from their Aqueous Solutions . . . . . . . . . . 386
PA2-27 A. Mahmoud, et al.,
A Comparative Study of Radiation Sterilization of Cell Cul-
ture Media and Filtration Sterilization Method in Cell Cul-
ture Laboratory . . . . . . . . . . . . . . . . . . . . . . . . . . 387
PA2-28 D. Mandal, et al.,
SimultaneousRadiationGrafting ofAcrylicAcid onPolypropy-
lene Films: Optimization, Biodegradability and Evaluation
of Ecotoxicological Impact . . . . . . . . . . . . . . . . . . . . 388
72
ICARST–2017
PA2-29 K. Marušić, et al.,
Metal Surface Modification with Fatty Acids Using Ionizing
Radiation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 389
PA2-30 K. Marzouki, et al.,
Irradiation Effects on Structure and Spectroscopic Properties
of Sugar Doped Sol-Gel Silica . . . . . . . . . . . . . . . . . . 390
PA2-31 S. Mohd Janib, et al.,
Ionizing Radiation Engineered Functional Nanogels for Bio-
medical Applications . . . . . . . . . . . . . . . . . . . . . . . 391
PA2-32 M. Z. I. Mollah, et al.,
Effect of γ-Radiation on the Physico-Mechanical Properties of
Gelatin-Based Films and Jute-Reinforced Polymer Composites392
PA2-33 M. Negrin, et al.,
Ionizing Radiation as a Tool to Affect Polymer Biodegradation393
PA2-34 N. G. Nik Salleh, et al.,
Development of Nanocomposite Coatings by Radiation Curing394
PA2-35 H. Nizam El-Din, et al.,
Swelling andDrugReleaseKinetics of Polyacrylamide/Sodium
Alginate Copolymer Hydrogels Synthesized by γ-Irradiation 395
PA2-36 R. Papaléo, et al.,
Effect of Spatial Confinement on the Radiolytic Efficiency of
High-Energy Ions in Polymers . . . . . . . . . . . . . . . . . 396
PA2-37 E. Pérez, et al.,
Functionalization of Polypropylene FilmswithGlycidylMeth-
acrylate by γ-Radiation . . . . . . . . . . . . . . . . . . . . . 397
PA2-38 M. P. Pérez-Calixto, et al.,
Synthesis and Characterization of PP Films Rich in Primary
Amines for Cell Cultures, by γ-Radiation . . . . . . . . . . . 398
PA2-39 T. Piroonpan, et al.,
Biopolymer-Silver Nanoparticle as a CIELAB Colour Space
Dosimeter . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 399
PA2-40 I. Pucić, et al.,
NanocarbonBasedPolyLY(Ethylene-Terephthalate)Nanocom-
posites and Various Irradiations . . . . . . . . . . . . . . . . 400
PA2-41 A. Raafat, et al.,
In Situ Deposition of Nanohydroxyapatite within N,O-Carb-
oxymethylchitosan/Polyvinylpyrrolidone Hydrogels: Char-
acterization and Bioactivity Evaluation . . . . . . . . . . . . 401
PA2-42 A. Radosavljević, et al.,
Morphological, Physico-Chemical and Mechanical Proper-
ties of Radiolytically SynthesizedNano-Ag/poly(N-isopropyl-
acrylamide) Hydrogels . . . . . . . . . . . . . . . . . . . . . . 402
73
ICARST–2017
PA2-43 N. Rahman,
Preparation of Selective Hazardous Metal Ion Adsorbents
from Acrylic Monomer Grafted PET Films . . . . . . . . . . 403
PA2-44 M. Rapado Paneque, et al.,
Nanogels of Polyvinylpyrrolidone Obtained by γ-Radiation:
Physicochemical and Biological Characterization . . . . . . . 404
PA2-45 S. Y. Ratnayake, et al.,
Chemical Reduction of Nitrate by Zerovalent Iron Nanopar-
ticles Adsorbed Radiation Grafted Copolymer Matrix . . . . 405
PA2-46 A. Sagatova, et al.,
Lifetime Study of Electronic Devices for Extreme Radiation
Conditions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 406
PA2-47 F. Saghatchi, et al.,
The Hormetic Effect of X-Rays on Biosynthesis of Gold Nano-
particles by Actinobacteria . . . . . . . . . . . . . . . . . . . . 407
PA2-48 M. Salla Ferreira, et al.,
Correlation of Traditional and One-Step Irradiation Process
for Chitosan Production from Charybdis Hellerii Crab Shells 408
PA2-49 H. Sayed,
Effect of γ-Irradiation on theMolecularWeight and Structure
of Guar Gum . . . . . . . . . . . . . . . . . . . . . . . . . . . 409
PA2-50 S. Shayanfar, et al.,
Investigations on Immobilizing Anthocyanin and Betacyanin
onto Polyethylene Films . . . . . . . . . . . . . . . . . . . . . 410
PA2-51 N. A. Shukri, et al.,
Shelf Life Assessment of Sliced Bread by Sorbic Acid Based
Active Film . . . . . . . . . . . . . . . . . . . . . . . . . . . . 411
PA2-52 J. Spasojević, et al.,
Structural Characterization, Antibacterial Properties and
Citotoxicity of γ-Irradiation SynthesizedAg-poly(N-isopropyl-
acrylamide/itaconic acid) Hydrogel Nanocomposites . . . . 412
PA2-53 I. Tartaro Bujak, et al.,
The Effect of Natural Antioxidiants in Thiyl Radical-Induced
Lipid Modification Processes . . . . . . . . . . . . . . . . . . 413
PA2-54 T. M. Ting,
Evaluation of Thorium Adsorbent Prepared by Radiation
Grafting and Functionalization with Glucamine . . . . . . . 414
PA2-55 M. Wang,
γ-Ray-Radiation-Scissioned Chitosan as a Gene Carrier and
its Improved in vitro Gene Transfection Performance . . . . 415
PA2-56 Y. Yin, et al.,
In Situ Compatibilization of Polyblends and Polymer Based
Composites Induced by γ-Irradiation . . . . . . . . . . . . . 416
74
ICARST–2017
PA2-57 J.-M. Yun, et al.,
Low Dimensional Nanomaterials-Based Interfacial Engineer-
ing in Organic Solar Cells . . . . . . . . . . . . . . . . . . . . 417
PA2-58 T. Zaharescu, et al.,
Radiochemical Stability and Life Time of LDPE-Based Flexi-
ble Composite Filled with Ce-Doped PZT-PbZrTiO3 . . . . . 418
PA2-59 A. Zaouak, et al.,
Decolouration andDegradation of Erythrosine by γ-Irradiation419
PA2-60 X. Zeng, et al.,
γ-Ray Induced Reduction andModification of Graphene Oxide420
PB: Posters PB: Radiation Technologies for Measurement . . . . . . . . . 421
PB-01 A. O. A. Abdelbari, et al.,
The Study of Industrial Process with Radioactive Tracer RTD
Method Enhanced System Analysis . . . . . . . . . . . . . . 422
PB-02 J. K. J. Al-Saedi,
The Concentrations of Major and Trace Elements in Pow-
dered Milk Using XRF and NAA, and Comparison to Other
Techniques . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 423
PB-03 A. Benahmed, et al.,
Development of a New Ambient Dosimetry Monitor for
In Situ Environmental Monitoring at the Nuclear Studies
Centre of Maâmora, Morocco . . . . . . . . . . . . . . . . . . 424
PB-04 K. Broce, et al.,
Study of Sediments in a Sub-Basin of the Panama Canal
Using Nuclear Techniques . . . . . . . . . . . . . . . . . . . . 425
PB-05 M. J. G. Gichuru, et al.,
Tracers of High Altitude Pollution Sources and Impact on
Mt. Kenya Ecosystem . . . . . . . . . . . . . . . . . . . . . . . 426
PB-06 M. Goes Nunes, et al.,
CaSO4:Dy and CaSO4:Ce,Eu Intrinsic Efficiencies Depen-
dence on Ionizing Radiation Type and Quality . . . . . . . . 427
PB-07 V. Khoury Asfora, et al.,
Evaluation of TL and OSL Response of CaF2:Tm for Electron
Beams Dosimetry in Radiation Processing . . . . . . . . . . 428
PB-08 J. D. R. Lopes Gomes, et al.,
Radiation Shielding Design Assessment of Nucleonic Gauges429
PB-09 A. H. Lopez Gonzales, et al.,
Axial Computed Tomography Phase-Space Source Model in
the PenEasy/PENELOPE Monte Carlo System: Implementa-
tion and Validation . . . . . . . . . . . . . . . . . . . . . . . . 430
75
ICARST–2017
PB-10 U. Mirsaidov,
Application of Radiation Science and Technology in the Re-
public of Tajikistan . . . . . . . . . . . . . . . . . . . . . . . . 431
PB-11 M. S. Mohammed, et al.,
Simulation Studies on the Image Quality of Industrial Film
Radiography . . . . . . . . . . . . . . . . . . . . . . . . . . . 432
PB-12 K. N. Myaing,
Comparison of Image Reconstructions for γ-Transmission
Computed Tomography System by Using MATLAB and i-
Gorbit Software . . . . . . . . . . . . . . . . . . . . . . . . . . 433
PB-13 H. K. Namburi, et al.,
Neutron Radiography Studies for Detection of Hydrogen
Distribution in Nuclear Fuel Claddings at Research Centre Řež434
PB-14 J. Phirani, et al.,
Adsorption Behaviour of Chloroauric Acid, a Generic Ad-
sorbing Tracer, for Finding Wetting Behaviour of Fluids in
Oil and Gas Industry . . . . . . . . . . . . . . . . . . . . . . . 435
PB-15 A. Quaranta, et al.,
Ion Irradiation Effects on the Optical Properties of Quantum
Dots for Nano-Dosimetric Systems . . . . . . . . . . . . . . . 436
PB-16 M. Rodríguez Alayón, et al.,
Results of Radiation Protection in Practices with Sources of
Ionizing Radiation in the Petroleum Refining Industry . . . 437
PB-17 M. I. A. Sagiroun, et al.,
Radiation Dosimetry of Laboratory Practices based on Ra-
diotracers Techniques . . . . . . . . . . . . . . . . . . . . . . 438
PB-18 M. Schoebel, et al.,
Application of Complementary Beam Techniques to Study
Deformation Mechanisms in Heterogeneous Materials for
Automotive Industry . . . . . . . . . . . . . . . . . . . . . . . 439
PB-19 L. Sereeter, et al.,
Neutron Activation Installments for Control of Flour Spar
Enriching Factory in Mongolia . . . . . . . . . . . . . . . . . 440
PB-20 T. Smolinski, et al.,
Synthesis Method of Multimodal Radiotracers for Industrial
Processes and Environmental Research . . . . . . . . . . . . 441
PB-21 S. Sugiharto, et al.,
Examination the Performance of the Trayed Ethylen Produc-
tion Column Using γ-Ray Scan Techique . . . . . . . . . . . 442
PB-22 I. D. A. Sutapa,
Resident Time Determination of IPAG60 in Order to Increase
Efficiency of Drinking Water Treatment Plant for Peatland
Area . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 443
76
ICARST–2017
PB-23 T. Weerakkody Appuhamillage, et al.,
Terrestrial Background Radiation in Norochcholai in the
North Western Coast of Sri Lanka . . . . . . . . . . . . . . . 444
Indexes 445
Relevant Publications 462
IAEAMeetings 464
77

ICARST–2017
OP:Opening Plenary
79
OP
OP-04 Talk: Session OP, Monday 10:30 Chmielewski
Ionizing Radiation: Innovative and Effective Tool for Science
and Industry
A. G. Chmielewski1
1Institute of Nuclear Chemistry and Technology (INCT), Warsaw, Poland
Corresponding Author: A. G. Chmielewski, a.chmielewski@ichtj.waw.pl
Ionizing radiations in the form of γ-rays, energetic electrons and X-rays (Bremsstrahlung)
are being used for many practical applications. Successful irradiation processes provide
significant advantages in comparison to typical thermal and chemical processes, such as
higher throughput rates, reduced energy consumption, less environmental pollution, more
precise process control and products with superior qualities. Ionizing radiation can modify
the physical, chemical and biological properties of materials on an industrial scale. Many
γ-sources and electron accelerators were built and installed for these purposes over the past
fifty years and the field is still expanding. The biggest industrial use of ionizing radiation is
the modification of polymer properties in a variety of industrial applications such as wire
and cable insulation, tire manufacturing, production of polymeric foams, hydrogels and
heat-shrinkable films and tubing, curing of coatings, adhesives and composites. Ionizing
radiation became a perfect tool for formation and synthesis of nanoparticles and nanocom-
posites. Sterilization by ionizing radiation accounts for the preparation of approximately
50% of single use medical devices in UK and 40–50% of all disposable medical products in
North America. Radiation technologies may also be applied to environmental protection
and cultural heritage preservation. Efficient radiation technologies for gas, liquid and solid
wastes treatment were developed to reduce environmental degradation. Cultural heritage
artefacts based on paper, textiles or wood are prone to biological attack and their disinfection
using ionizing radiation has been successfully demonstrated. Another field of applications
is based on ionizing radiation penetration properties and its precise detection, through
utilization of open and sealed radiation sources. Optimization of industrial processes is
essential not only for efficient, safe and sustainable operation, but also to save materials,
energy, protect the environment and reduce plant shutdown time. Complex industrial
processes include environmentally related processes (such as harbours and dams, oil fields
and ore/coal mines) so it is essential to have suitable means to investigate them for process
optimization and trouble-shooting—preferably without shutting down the plant or pro-
cess. Radiotracers and sealed source techniques are best-suited methods to address these
problems. Nuclear techniques in most of the cases provide on-line investigations without
shutting down the plant or process. Automation and improvements in instrumentation
and hardware, such as tracer injection systems, detectors and data acquisition systems are
developed for safer and reliable application. All applications are based on science developed
in universities and research centres and then transferred to industry to be used in a safe and
proper manner. It is a joint input of scientists and professionals working in the field to the
main UNMillennium Goals of achieving a resource-efficient and climate-change-resilient
economy and society, protecting and sustainably managing natural resources and ecosys-
tems, and ensuring a sustainable supply and use of raw materials and other environmental
resources. This universal humanistic role of science was articulated by Madame Curie, a
lady born exactly 150 years ago in Warsaw as Maria Skłodowska. She developed a new
innovative and effective tool— ionizing radiation—which broke new ground in physics
and chemistry, opening the door for advances in engineering, biology and medicine.
80 IAEA–CN–241–457
OP
ICARST–2017
A01:Trends in Radiation Science and Technology
81
A01
A01-01 Talk: Session A01, Monday 11:15 Ulański
Radiation Synthesis of Polymer Nanogels for Biomedical
Applications
P. Ulański1
1Institute of Applied Radiation Chemistry, Lodz University of Technology, Łódź, Poland
Corresponding Author: P. Ulański, ulanskip@mitr.p.lodz.pl
One of the most rapidly developing fields of nanotechnology is nanomedicine. Creation of
nanoscale materials which could be transported via the cardiovascular system, penetrate
cellular membranes and selectively target specific tissues or organs opens a new range of
possibilities for controlled drug delivery, gene therapy, radiotherapy, etc. An important
class of nanoparticles for medicine are nanogels.
Nanogels can be defined either as tiny fragments of hydrogel networks, or as internally
cross-linked single macromolecules. Classical polymer chemistry offers several ways to
synthesize polymer nanoparticles, but most of them require complex procedures and the
use of monomers, cross-linking agents, initiators, surfactants, which are difficult to remove
from the final product, while some of themmay be toxic. Since the late 1990’s, an alternative
approach based on radiation chemistry has been proposed and developed, where the only
substrates are polymer chains and solvent (usually water). The basic idea of this technique
is to irradiate a dilute polymer solution in such a way that many radicals are present
simultaneously on each macromolecule. Their intramolecular recombination creates new
covalent bonds linking the segments of the polymer chain and thus a nanogel particle is
formed. Understanding the mechanism and kinetics of these processes can be facilitated by
using pulse radiolysis and Monte Carlo simulations. Procedures have been developed to
synthesize nanogels having their mass and size tailored to meet specific needs.
This talk, besides presenting the basics of radiation synthesis of nanogels and recent de-
velopments from authors’ lab, is also intended to briefly summarize important progress in
this field achieved by teams from many countries. Co-operation between these research
groups has been greatly facilitated by a number of recent CRPs on these topics, initiated
and coordinated by IAEA.
82 IAEA–CN–241–422
A01
Shen Talk: Session A01, Monday 11:35 A01-02
Status and Prospect of Application of Radiation Science and
Technology in China: A National Report
L. Shen1
1China Atomic Energy Authority (CAEA), Beijing, People’s Republic of China
Corresponding Author: L. Shen, shenlx@cnnc.com.cn
As an emerging strategic industry supported by the Chinese government, application of
radiation science and technology has seen rapid development in recent years and is now at
its golden age of fast development. The annual output of the industry in China has exceeded
300 billion RMB yuan (approximately 46 billion USD) in 2016, which is expected to maintain
an annual growth of 15% to 20%.
Entrusted by the China Atomic Energy Authority (CAEA) and other related ministries, the
Chinese Nuclear Society (CNS) has carried out a two-year-long nation-wide survey on this
industry of radiation science and technology application since late 2015 in order to have an
overall idea of the major achievements in the past ten years, its important role in improving
people’s living and health and the opportunities and challenges facing the industry in order
to predict its development trend in future. A comprehensive report is under preparation.
This paper present the key outcome of the survey. Part one provides a general description
of the development status of application science and technology in China. Part two details
on China’s efforts in development ray source such as accelerator, isotope, and related
integrated installations based on accelerator or with γ-ray, inspection equipment based on
ray imaging, non-destructive inspection equipment, etc. Part three introduces more in detail
the application of radiation science and technology in industry, agriculture, health care,
environment protection, and national security in China. Part four sketches China’s effort in
education and training for this industry. Part five estimates the prospect of the application
of radiation science and technology in China in the future.
IAEA–CN–241–452 83
A01
A01-03 Talk: Session A01, Monday 11:55 Croonenborghs
Emerging Areas of Radiation Sterilization
B. Croonenborghs1
1Sterigenics, Oak Brook, IL 60523, USA
Corresponding Author: B. Croonenborghs, bcroonenborghs@eu.sterigenics.com
Since the installation of the first γ-irradiators for sterilization of single-use healthcare prod-
ucts in the 1960’s, this application of ionizing radiation has evolved into a mature industry
where now roughly 40%–50% of all single-use healthcare products are radiation sterilized.
With the development of ever more complex healthcare products, new challenges for devel-
oping, establishing and controlling a radiation sterilization process have come across the
industry. Customized solutions need to be developed in order to be successful in this area.
Examples of such processes qualified within the Sterigenics network of gamma and high
energy electron beam irradiators are presented.
84 IAEA–CN–241–448
A01
Abad Talk: Session A01, Monday 12:15 A01-04
Radiation-Modified Carrageenan as Plant Food Supplement:
Making a Breakthrough with Philippine Farmers
L. V. Abad1, D. R. Montefalcon1, F. Aurigue1, R. M. Dela Cruz1, G. Magsino2, and
A. Carpio3
1Philippine Nuclear Research Institute (PNRI), Quezon City, 1107 Metro Manila, Philippines
2National Crop Protection Center (NCPC), Crop Protection Cluster (CPC),
University of the Philippines Los Baños College of Agriculture (UPLB), Los Baños, Laguna, Philippines
3Philippine Council for Agriculture, Aquatic and Natural Resources Research and Development (PCAARRD),
Los Baños, Laguna, Philippines
Corresponding Author: L. V. Abad, lvabad@pnri.dost.gov.ph
Radiation processing of kappa carrageenan by either γ-or EB irradiation produces low
molecular weight fragments that can induce growth promotion effects on plants. The
fragments that are produced have an average molecular weight (MW) of less than 10 kDa.
These low MW kappa carrageenan increases yield in Pechay plants when applied either by
foliar spraying or in hydrophonics condition. r1s Recent studies in the Philippines indicated
improved agronomic traits with a dramatic increase in yield in mungbean and peanut
plants of 200–400% and 150–200%, respectively using screen house experiments. Field
experiments in mungbean produced around 10 times higher yield than the normal farmer’s
practice.
Multi-location trials of around 2000 ha rice field in different regions of the Philippines
indicated an average increase in yield of 15–30% compared to normal farmer’s practice.
Highest yield of as much as 60% was obtained. Increased resistance to tungro virus was also
noted. Likewise, there was extensive root growth and sturdy stems that prevent lodging of
rice plant. Testimonies given by farmers indicated a substantial increase in their income
with the utilization of radiation-modified carrageenan.
Degradation of κ-carrageenan by EB irradiation is inhibited by the formation of cross-links.
Optimization by addition of hydrogen peroxides to improve degradation is discussed. Data
on pilot scale production of radiation-modified carrageenan is presented.
References
r1s L. V. Abad, et al., Radiation Physics and Chemistry 118, 75–80 (2015).
IAEA–CN–241–049 85
A01
A01-05 Talk: Session A01, Monday 12:35 Wishart
Recent Progress in Pulse Radiolysis Detection Methods and their
Application to Ionic Liquid-Based Systems for Closing the
Nuclear Fuel Cycle
J. Wishart1, A. Cook1, and D. Grills1
1Brookhaven National Laboratory (BNL), Upton, NY 11973, USA
Corresponding Author: J. Wishart, wishart@bnl.gov
Recent developments in instrumentation have opened up new vistas for radiation research
using pulse radiolysis techniques. Picosecond pulse radiolysis has become a routine tech-
nique in several countries, and new techniques are under development to further expose
physical events occurring at very short times following radiolysis. Optical fibre-based
“single-shot” methods providing picosecond-timescale transient spectroscopy detection
for sub-millilitre liquid and solid samples now exist. New technologies such as mid-IR
quantum cascade lasers enable detailed mechanistic studies of radiation-induced reactions
using the high resolution and structural specificity of vibrational spectroscopy to identify
intermediates. Broadband multispectral detection has increased the power and throughput
of pulse radiolysis detection methods in the infrared and UV-Vis-NIR. In addition to the
current progress described above, a perspective will be offered identifying important areas
for future instrumentation development in support of cutting-edge radiation science.
Ionic liquids (ILs) attract the interest of researchers and industry due to their remarkable
properties, and many applications in the fields of energy and technology, including as a
potential medium for the treatment of spent nuclear fuel for the sustainable use of nuclear
energy. For several years we have studied aspects of ionic liquid radiation chemistry from
primary species reactivity through long-term product accumulation, to elucidate their
degradation pathways. We aim to develop innovative, effective and durable IL-based
separations systems, so we must also describe how radiolysis interferes with the separation
process. During this project we found several classes of ions that are resistant to ionizing
radiation and we will present some examples. The recent development of mid-infrared
transient absorption detection has been particularly useful. For example, we observed the
immediate formation of acetaldehyde and vinyl alcohol during pulse radiolysis of choline
NTf2.
This work and use of the LEAF Facility of the BNL Accelerator Center for Energy Research,
were supported by the U.S. Department of Energy, Office of Basic Energy Sciences, Division
of Chemical Sciences, Geosciences and Biosciences, under contract DE-SC0012704 (BNL).
86 IAEA–CN–241–385
A01
Vasquez Talk: Session A01, Monday 12:55 A01-06
Overview of Disinfection of Cultural Heritage Artefacts and
Archive Materials by Ionizing Radiation in Brazil: Culture Meets
Nuclear
P. Vasquez1
1Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), São Paulo, Brazil
Corresponding Author: P. Vasquez, pavsalva@usp.br
Brazil is a multicultural South American country has had the influence of the pre-Columbian
native civilizations, the Portuguese and African colonization and lately the European colo-
nization especially from Germany and Italy, not to mention that Brazil is home to the largest
Japanese population outside Japan. In addition other factors, this situation makes the coun-
try own a vast variety collection of historic value objects. Brazilian weather conditions have
been affected directly tangible materials causing deterioration besides on insects and fungi
attack. Natural disasters particularly floods also have been affected many collections inside
the country. Within this scenario, the γ-radiation processing arises as an alternative to
traditional methods to the disinfection of cultural heritage artefacts and archived materials.
Over the last years, the Nuclear and Energy Research Institute (IPEN), mainly through the
Multipurpose Gamma Irradiation Facility located inside the São Paulo University campus,
started a strong interaction programme with conservation and preservation institutions and
too with the conservation community to disclose the irradiation technique. Currently, this
facility has irradiated for disinfection purposes effectively several works of art, museum
collections artefacts, books, manuscripts, drawings, archive documents, musical instru-
ments, ethnographic objects, archaeological findings, natural history collections among
others from various regions of the country. γ-irradiation has several advantages when
compared with conventional preservation methods mainly related to the safety, efficiency,
reliability, capacity, process time and safe for environment. The success obtained in Brazil
with these applications is due to the support of the IAEA to many regional projects related
to the nuclear techniques applied to cultural heritage preservation and research. The IAEA
policies are helping to understand that the cultural heritage is a legacy of physical artefacts
and intangible attributes of a group or society that are inherited from past generations,
maintained in the present and restored for the benefit of future generations.
IAEA–CN–241–453 87
A01
ICARST–2017
A02:Advanced Polymeric Materials
88
A02
Güven Talk: Session A02, Monday 14:15 A02-01
Past, Present and Near Future of Radiation Processing of
Polymers
O. Güven1
1Hacettepe University, Ankara, Turkey
Corresponding Author: O. Güven, guven@hacettepe.edu.tr
In the early years of radiation processing, radiation-induced cross-linking of polymers
and radiation sterilization of medical products have developed into substantial industries.
Radiation processing of polymers in its widest sense is the application of radiochemical
effects of ionizing radiations (γ-rays, X-rays, accelerated electrons, and swift heavy ions) on
polymers and plastics on industrial scale. When polymers are irradiated with high energy
radiation the ultimate effects are observed as cross-linking and/or scissioning of main or
side chains, grafting, curing and formation of oxidized products. Among the established
industrial applications of radiation processing of polymers; cross-linking of insulation of
cables and wires, preparation of heat-shrinkables, polymer foams, automotive parts, tyres,
water distribution pipes, tubes, plastic medical devices, hydrogel burn andwound dressings,
composites, controlled degradation of teflon andmarine-based cellulosics can be mentioned.
The field of lignocellulosic fibre-polymer composites utilizing radiation technology in their
formulation is re-emergingr1s.
The applications mentioned above are based on radiation-induced control of structure
formation in polymers on macroscopic scale, with the growing interest on development
of nanomaterials based on polymers. However, the unique role and power of ionizing
radiation in nanostructuring have been rediscovered. Nanostructure formation by using
ionizing radiation encompass a wide range of products namely, nanocomposites, nanogels,
metallic nanoclusters, surface grafting at nanoscale, functionalization of track-etched mem-
branes, molecular imprinting. This review will highlight chronologically the milestones of
radiation processing of polymers in bulk, radiation-grafted materials for separation and
purificationr2s, for energy conversion and energy storager3s and health-care applications.
Established and emerging applications of radiation technology for nanotechnology will be
elaborated with a future outlook.
References
r1s O. Güven, et al., submitted to Polymer Reviews, (2016).
r2sM. M. Nasef and O. Güven, Prog. Polym. Scien., 37, 1597–1606 (2012).
r3sM. M. Nasef, et al., submitted to Prog. Polym. Scien., (2016).
IAEA–CN–241–337 89
A02
A02-02 Talk: Session A02, Monday 14:35 Coqueret
Radiation Curing by Cross-Linking Polymerization of
Multifunctional Monomers: A Comparison Between Free
Radical and Cationic Mechanisms
X. Coqueret1
1Universite de Reims Champagne–Ardenne, 51100 Reims, France
Corresponding Author: X. Coqueret, xavier.coqueret@univ-reims.fr
Radiation-curing by polymerization of multifunctional monomers is a well-established
technology in the field of coatings and adhesives as well as in the graphic arts. UV-visible
light and high energy radiation are alternative activation processes exhibiting their specific
scope, advantages, and limitations depending on the application. The situation is quite
different when the industrial goal is to cure thick and large parts of composites reinforced
by fillers or by fibrous materials that induce opacity with respect to UV visible light. High-
energy radiation processing has been identified since decades as a promising method for
performing out-of-autoclave curing, with several advantages in terms of processing time,
energy consumption, environmental footprint and sanitary concerns. The challenging
objective of developing the EB/X-ray curing technology for high performance composite
materials drives the needs of the advanced knowledge and understanding of reactivity to
structure to properties inter-relations. Our paper will focus on the nanostructural features
of radiation-cured networks.
The radiation-induced polymerization of multiacrylate monomer compositions is known to
proceed heterogeneously at various dimension scales, depending of monomer composition.
In radiation-cured materials based on a single type of monomer, the network were shown to
display heterogeneities of cross-link densities resulting from a complex interplay between
mechanistic and kinetic factors along the solidification process. Compared to free-radical
chain polymerization, radiation-initiated cationic polymerization exhibits peculiarities at
the different steps of the chain process (complex initiation and propagation mechanisms,
pseudo-living character, . . . ). The influence of these features on the reactivity and on the
microstructure of multifunctional aromatic epoxy monomers and of their acrylate analogs
has been examined using various types of radiation (UV, visible, EB, X-ray). Complementary
spectroscopic and analytical methods were implemented in order to correlate the changes
of network physical properties with the progress of polymerization.
AFM analysis of the networks in the topographic, phase contrast and indentation modes
provides quite informative data with indications on the actual dimensions of the soft and
rigid domains, and of their evolution, as the curing level is driven to higher values.
Solid-state proton T2 NMR relaxation experiments were also performed on radiation-cured
materials with valuable quantitative information on the local mobility in the nanoheteroge-
neous samples as well as on the associated fraction of material, as polymerization proceeds.
On the basis of these observations and measurements, a consistent scenario for the build-up
of radiation-cured networks is proposed for both types of polymerization mechanisms. The
influence of this general behaviour is discussed in the perspective of elaborating materials
with demanding use properties.
90 IAEA–CN–241–290
A02
Lacroix Talk: Session A02, Monday 14:55 A02-03
Use of Irradiation, for the Development of Active Edible
Coatings, Beads and Packaging to Assure Food Safety and to
Prolong Preservation
M. Lacroix1
1INRS-Institut Armand-Frappier, Canadian Irradiation Centre, Laval, QC H7V–1B7, Canada
Corresponding Author: M. Lacroix, monique.lacroix@iaf.inrs.ca
There is a need to develop active packaging and active edible coating by using natural
ingredients. To reduce the pollution problems caused by synthetic and non-biodegradable
packaging films, biodegradable packaging materials are encouraged to be developed espe-
cially in case of antimicrobial packaging. Also, the consumer demand to replace synthetic
antimicrobial by natural compounds is rising. However, natural antimicrobials are not stable
and should be encapsulated or immobilized in polymers to preserve their bioactivity and
to assure a control release of the active compounds during time. Edible polymers should
possess the appropriate barrier and chemical properties and should retain its properties
during commercial marketing of foods. Proteins and polysaccharides have been used to
develop edible coatings, beads and biodegradable films. However, these polymers are
soluble in water and their functional properties should be improved. This presentation will
focus on the use of cross-linking and functionalization of polymers by γ-irradiation for the
development of active edible coating, beads and packaging and the use of γ-irradiation in
combination with these active polymers to assure food safety.
IAEA–CN–241–007 91
A02
A02-04 Talk: Session A02, Monday 15:15 Ghazali
Radiation Grafted Antimicrobial Film for Advanced Active
Packaging Application
Z. Ghazali1, N. A. Shukri1, and N. A. F. Othman1
1Malaysian Nuclear Agency, Bangi, 43000 Kajang, Selangor, Malaysia
Corresponding Author: Z. Ghazali, zulkafli@nm.gov.my
Low density polyethylene (LDPE) film was grafted with sorbic acid (SA) using radiation
induced grafting (RIG) technique to develop advanced antimicrobial grafted film for active
packaging application. Instead of mixing antimicrobial additive as food additive directly
with food, this additive was incorporated in films via RIG and allowed the functional
effect at the food surface, where microbial growth is mostly found. Therefore, removal or
reduction of preservatives from food formulate with non-migratable additives increases
food safety andmeets consumer demands for fresher food. The evidences of sorbic acid (SA)
grafting film were studied using grazing-angle Fourier transform infra-red spectroscopy
(GA-FTIR), field emission scanning electron microscope (FESEM), atomic force microscopy
(AFM) and X-ray photoelectron spectroscopy (XPS). The antimicrobial properties of LDPE
film functionalized by sorbic acid were evaluated with respect of its mechanical properties
and surface properties. The analysis of fungi killing time during storage of freshly baked
bread packed in grafted shows a significant antimicrobial efficacy on food indicating the
potential of grafting of this active agent on a LDPE film instead of adding it in the food
itself.
92 IAEA–CN–241–184
A02
Vasile Talk: Session A02, Monday 15:35 A02-05
Radiation Mediated Bioactive Compounds Immobilization on
Polymers to Obtain Multifunctional Food Packaging Materials
C. Vasile1, E. Stoleru1, B. Multeanu2, T. Zaharescu3, and E. Ioanid1
1Institute of Macromolecular Chemistry “Petru Poni”, 700487 Ias, i, Romania
2Alexandru Ioan Cuza University, Ias, i, Romania
3National Institute of Research and Development for Electrical Engineering (ICPE-CA), Bucharest, Romania
Corresponding Author: C. Vasile, cvasile@icmpp.ro
Irradiation of polymeric surface is a versatile way to implement specific functionalities which
further can react with bioactive compounds in order to confer to materials antimicrobial,
antioxidant and biological functions absolutely necessary to protect, prolong self life of food
products and make them beneficial for health.
Both undegradable and degradable polymers were exposed in optimal conditions to γ-rays
or cold plasma in various atmospheres (air, oxygen, nitrogen) and oxygen- and nitrogen-
containing groups were reacted with chitosan, vitamin E and C and vegetable oils with
high therapeutic value encapsulated in nanostructures obtained by co-axial electrospinning
or emulsion techniques. The nanoencapsulation of active (antimicrobial and antioxidant)
vegetable oils into chitosan matrix by leads to a significant decrease of total viable counts
when compared with the PLA substrate plasma pretreated and surface modified only with
chitosan. The bioactive layer was covalently linked onto a polymeric substrate so it is stable,
and compounds do not migrate in food products and bulk properties of base materials are
not changed.
Bioactive multifunctional polyethylene based food packaging with antimicrobial activity
against both gram positive and gram negative bacteria and antioxidant activities have
been obtained. Use of chitosan/vegetable oils shows synergistic activities. Two other
biodegradable substrates as polylactic acid and cellulosic materials (cellulose/chitin blends
and kraft papers) were subjected to the same procedures with very promising results,
moreover, these are easily recyclable and integrate into environment after use. Assessment
of degradation of materials was investigated by enzymatic degradation in presence of
phanerochaete chrysosporium by biochemical investigation (superoxide dismutase activity
in fungi mycelium samples, content of malondialdehyde, catalase enzyme, extracellular
protein), changes in average molecular weight, ATR-FTIR and AFM. The plasma and γ-
radiation exposed PLA and PLA/CHT stratified composites supported fungal growth
resulting in their degradation, which is reflected in change in polymeric substrate structure.
The presence of bioaccessible material, i.e., PLA and chitosan, facilitated degradation. The
plasma and γ-irradiated PLA samples show increased degradation. Natural and synthetic
polymeric substrates, plasma activated and/or γ-irradiated, were tested as active-food
packaging to improve the shelf-life of poultry meat, fresh beef meat, fresh curd cheese and
apple juice. Rosehip seed oil was found to impart the best antioxidant and antimicrobial
properties.
By comparison of γ-rays or cold plasma exposure we can conclude that γ-irradiation is
more efficient in terms of bioactive functions of obtained materials.
IAEA–CN–241–142 93
A02
A02-06 Talk: Session A02, Monday 15:55 Hegazy
Radiation Processing of Natural and Synthetic Polymers for
Potential Applications
E. Hegazy1, H. A. Abd El-Rehim1
1Egyptian Atomic Energy Authority (EAEA), Cairo, Egypt
Corresponding Author: E. Hegazy, hegazy_ea@hotmail.com
The effect of ionizing radiations on the cross-linking and degradation of some natural
polymers such as CMC-Na, chitosan, carrageenan, alginates and starch was investigated.
Trials were made to control and reduce the irradiation dose required for the CMC-Na
degradation by the addition of some additives and controlling the irradiation conditions.
The possibility to cross-link CMC-Na/PAAm and starch/PAAm blends using electron
beam irradiation to obtain good adsorbent materials of unique properties for possible
practical uses were also investigated. The end product of irradiated natural products such
as carboxy-methylcellulose, chitosan and Na-alginate may be used as food additive or
benefited in agricultural purposes. From an economic point of view these doses are not
accepted, it was significantly reduced by the addition of APS, KPS and H2O2. The addition
of such additives to chitosan or Na-alginate during irradiation process accelerates their
degradation. Degraded Na-alginate and chitosan could be used as growth promoter for
plants in agriculture purposes. The growth and other responses of Zeamaze and bean plants
that treated with irradiated Na-alginate or chitosan of different Mw’s were investigated.
The test field results showed that the treatment of the zea plant with irradiated Na-alginate
or chitosan enhanced the plant growth and increases its productivity.
Chemically cross-linked, pH-sensitive PVP/PAAc hydrogel nanoparticles were successfully
prepared in a high yield via γ-radiation-induced polymerization of acrylic acid in aqueous
solution of poly(vinylpyrrolidone) (PVP) as a template polymer. The particle sizes of the
PVP/PAAc nanogels at different pH values were evaluated using dynamic light scatter-
ing (DLS) and the morphology was assessed using atomic force microscopy (AFM) and
transmission electron microscopy (TEM). Smaller and more stable nanogel particles can be
produced by irradiating a feed solution of 50–75mol%AAc and using PVP of highmolecular
weight. Factors affecting size and encapsulation efficiency were optimized to obtain nanogel
sufficient to entrap drug efficiently. The use of PVP/PAAc nanogels prepared at different
compositions and irradiation doses was evaluated for dry eye syndrome application.
94 IAEA–CN–241–079
A02
ICARST–2017
A03:Advances and Trends in Radiation Science and
Technology
95
A03
A03-01 Talk: Session A03, Monday 16:30 Zhai
Novel Ion Exchange Membranes Synthesized by Radiation
Grafting Technique for Application in Vanadium Redox Batteries
M. Zhai1, J. Ma1, and J. Peng1
1Peking University, Haidian, Beijing, People’s Republic of China
Corresponding Author: M. Zhai, mlzhai@pku.edu.cn
Vanadium redox battery (VRB) has attracted more and more attention as energy storage
system due to its long cycle life, deep discharge ability, high energy efficiency and low
cost. The ion exchange membrane (IEM) is one of the key components of VRB to pre-
vent the crossover of vanadium ions, and allow the transport of ions to complete the
conducting circuit. The ideal IEM should possess low permeation rates of vanadium
ions to minimize self-discharging, high conductivity, good chemical stability and cost-
competitiveness. The current available commercialmembranes cannot satisfy all of the above
requirements. In this report, a series of amphoteric ion exchange membranes (AIEMs) were
prepared by co-grafting of styrene/ N,N-dimethylaminoethyl methacrylate (DMAEMA),
α-methylstyrene/DMAEMA or sodium styrene sulfonate/DMAEMA binary monomers
into fluoropolymer films and sequent chemical reactions. The properties of the AIEM
strongly depended on the composition and grafting yield of the membrane, i.e., higher
content of DMAEMA brought lower permeability of vanadium ions, while higher grafting
yield led to higher water uptake, IEC and conductivity. By changing the conditions of the
grafting reaction, The AIEM exhibited high ion exchange capacity (IEC) and conductivity,
as well as significantly reduced permeability of vanadium ions. VRB assembled with the
AIEM maintained an open circuit voltage (OCV) higher than 1.3 V after placed for 300 h,
and exhibited higher Coulombic efficiency and energy efficiency than that with Nafion
117 membrane. Furthermore, the AIEM grafted DMAEMA and α-methylstyrene has high
chemical stability. The preparation of AIEM with grafting DMAEMA and sodium styrene
sulfonate avoids sulfonation, which is an environmental friendly process. In order to opti-
mize the synthesis method, radiation grafting technique and solution casting method have
been used to synthesize the AIEM by grafting styrene and DMAEMA into poly(vinylidene
fluoride) (PVDF) powder. This AIEM with new process could get higher conductivity than
traditional method using PVDF film as substrate, due to the uniform distribution of ion
exchange group in the AIEM. Based on the above experiments, an upscaling radiation
grafting technique has been developing for the preparation of the AIEM with an area of
850 mm ˆ 750 mm.
96 IAEA–CN–241–141
A03
Yu Talk: Session A03, Monday 16:50 A03-02
Irradiation Induced Modification of Nanoporous Metal Organic
Frameworks
M. Yu1, J. Li1, and Z. Wang1
1Shanghai Institute of Applied Physics (SINAP),
Chinese Academy of Sciences, Shanghai, People’s Republic of China
Corresponding Author: M. Yu, yuming@sinap.ac.cn
Metal organic frameworks (MOFs) are a class of nanoporous materials built from nodes of
metal clusters connected by organic ligands. The high specific area and abundant nanopores
have made MOFs promising in application such as gas storage, molecular separation,
heterogeneous catalysis and drug delivery. In the present work, the irradiation effect and
irradiation induced modification of MIL-101 (Cr) —a typical MOF material synthesized by
the coordination of Cr(III) ions with benzene-1,4-dicarboxylate ligand— was investigated.
The results of electron spin resonance (ESR) showed that the free radicals generated on
MIL-101 (Cr) after γ-ray irradiation were benzoyl free radicals and the concentration of
benzoyl radicals decayed with time upon storage. The reactivity of the benzoyl free radicals
on MIL-101 (Cr) was proved by the simultaneous graft polymerization of 2-hydroxyethyl
acrylate (HEA) onto the surface of MIL-101 (Cr) initiated by γ-irradiation. The grafting
kinetics of HEA on MOFs was similar to the conventional graft polymerization, which
indicated the irradiation induced grafting method can be used to modify MOFs just like the
irradiation induced modification of polymer materials. The PHEA graft chains significantly
increased the hydrophilicity of MIL-101 (Cr) and the contact angle of water on MIL-101 (Cr)
decreased from 156.7˝ to 61.5˝. Brunauer–Emmett–Teller (BET) surface area measurements
were performed to investigate the effect of grafting modification on the specific area of
MIL-101 (Cr). The results showed the specific area of the modified MIL-101 (Cr) increased
50% compared to that of as prepared MIL-101 (Cr), which should be attributed to the
accumulation of PHEA graft chains on the surface of the MOFs.
X-ray diffraction (XRD) was used to investigate the crystal structures of the as prepared
MOFs and the modified MOFs. The characteristic peak of the modified MIL-101 (Cr) was
almost the same as that of as preparedMIL-101 (Cr), which indicated the nanopore structure
of MOFs was not damaged by irradiation. In conclusion, HEAwas successfully grafted onto
the surface of MIL-101 (Cr) initiated by γ-irradiation. The specific area increased without
affecting the nanoporous structure of MIL-101 (Cr). The surface of MIL-101 (Cr) converted
from superhydrophobic to hydrophilic. The present work provides a new method for the
preparation of hydrophilic nanoporous materials.
IAEA–CN–241–258 Presenter: J. Li 97
A03
A03-03 Talk: Session A03, Monday 17:10 Burillo
Synthesis of Amine-Containing Surfaces in
Poly(Tetrafluoroethylene) by γ-Radiation
G. Burillo1, A. Hezael1, A. Cruz1, and J. C. Ruiz2
1Instituto de Ciencias Nucleares, Universidad Nacional Autónoma de México (UNAM), 04510 Ciudad de
México, Mexico
2Universidad Autónoma Metropolitana, Iztapalapa, Mexico
Corresponding Author: G. Burillo, burillo@nucleares.unam.mx
Amine grafting polymers can be useful surfaces for cell colonization, they are usually
prepared by plasma polymerization of alkylamine monomers. γ-radiation could be a good
method to graft severalmonomerswith amine groups in the desired polymer substrate as PE,
PP, PET, etc. In this study, amine surface in poly(tetrafluoroethylene) (PTFE) was obtained
by two different methods: a) grafting of acryloyl chloride by radiation direct method
and preirradiation peroxidation method of acryloyl chloride in dichloroethane solution
and further reaction with diethyldiamine; and b) preirradiation peroxidation grafting of
acrylic acid (AAc) onto PTFE, acylation reaction with SOCl2 and further reaction with
diethyldiamine. The grafting of AAc onto PTFE was studied before by Sadurni et al. (2000).
The grafting of acryloyl chloride onto PTFE was synthesized for the first time; the radiation
direct method was the best method with higher grafting yield. The effects of the monomer
concentration, absorbed dose, and reaction time were studied. The amount of amine
groups were evaluated, gravimetrically and the density of amine groups in the surface by
derivatization with 4-trifluoromethylbenzaldehyde (TFBA) followed by X-ray photoelectron
spectroscopy (XPS) analysis. Samples were also characterized by FTIR, contact angle, SEM
and AFM. Further studies will report the presence of a critical concentration of amine
groups to adhere different types of cell lines.
We thank A. Ortega, Martin Cruz, Luz Maria Escamilla and Luis Miguel Valdez from ICN
UNAM for the technical assistance and DGAPA UNAM grant 200116 for financial support.
98 IAEA–CN–241–051
A03
Kodama Talk: Session A03, Monday 17:30 A03-04
Polycarbonate Chromatography Column to Be Used in a
99Mo/99mTc Generator Irradiated in Saline Solution with EB
and γ-Rays
Y. Kodama1, R. Carneiro1, M. Rossi2, O. Rodrigues Júnior1, and P. Vasquez1
1Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), São Paulo, Brazil
2Universidade Presbiteriana Mackenzie, São Paulo, Brazil
Corresponding Author: Y. Kodama, ykodama@ipen.br
The technetium-99m generator (technetium cow or moly cow) is a device used to extract the
metastable technetium isotope 99mTc from a source of decaying molybdenum-99. 99Mo has
a half-life of 66 hours and can be easily transported over long distances to hospitals whereas
its 99mTc decay product (half-life of 6 h is inconvenient for transport) is extracted and used
for several nuclear medicine diagnostic procedures, where its short half-life is well adapted.
This device works as a closed system, where the principal component is a chromatographic
column of acid alumina (Al2O3) as stationary phase. Currently this column is produced
using borosilicate type 1 glass.
The goal of this study was to characterize the irradiated polycarbonate (PC) column in saline
solution to simulate a 99Mo/99mTc generator in real use conditions. PC column and PC sam-
ples were EB and γ-irradiated in saline solutionwith radiation absorbed doses up to 200 kGy.
Samples were analyzed by electron paramagnetic resonance spectroscopy (EPR), infrared
spectroscopy (FTIR), ultraviolet spectroscopy (UV), differential scanning calorimetry (DSC)
and wide-angle X-ray diffraction (WAXD). Additionally, the γ-irradiated PC column in pres-
ence of saline solution was studied using high performance liquid chromatography (HPLC)
coupled with fluorescence detection in order to investigate the chemical phase diffusion
of bisphenol A (BPA). EPR results showed at X band region a strong singlet attributed to
a phenoxyl radical in the irradiated sample at room temperature. Decay of radical occurs
approximately within 40 days. UV spectra presented increase in relative absorbance at
400–450 nm with increasing radiation dose. Ionizing radiation caused greenness of the
original clear PC samples. This discolouration confirms the formation of phenoxyl radicals.
On the other hand, glass transition temperature decreased by 1% (5K) for the maximum
radiation applied dose. Similarly, a small decrease on carboxyl group peak at 1770 cm´1
was observed by FTIR. No detectable change on crystallinity was observed by WAXD. For
sterilization absorbed dose, results shown no significant changes on the studied properties
that way can be recommend to use PC columns instead borosilicate glass column in the
99mTc generator. The protocol via HPLC with fluorescence detection used in this work
can be employed to detect the chemical phase diffusion of BPA in saline solution at ppb
concentration
IAEA–CN–241–061 99
A03
A03-05 Talk: Session A03, Monday 17:45 Dubois-Clochard
EB Irradiation on Piezo-PVDF: Beneficial Effect for Harvesting
Energy Application
M.-C. Dubois-Clochard1, G. Melilli1
1Laboratoire des Solides Irradiés (LSI/CEA), École Polytechnique, 91128 Palaiseau, France
Corresponding Author: M.-C. Dubois-Clochard, marie-claude.clochard@polytechnique.edu
Poly(vinylidene fluoride) (PVDF), is one of the most attractive semi-crystalline polymer
owing to its remarkable pyro-, piezo- and ferro-electric properties. These thermal and
electrical properties result from an appropriate crystalline phase arrangement inside PVDF
bulk. PVDF polymorphism is well-known and consists of four crystalline phases, named
α, β, γ and δ phases. In β phase, PVDF chains are arranged in pairs adopting an all-trans
planar zigzag conformation, resulting in a significant net dipole moment. Whatever the
phases, poling is a necessary ultimate step to align whole microscopic net dipole moment
to the direction of the electric field.
Since the discovery of the piezoelectric properties of PVDF in 1969, many research groups
immediately understood the potential applications of the polarized β-PVDF as sensors and
actuators. In the recent years piezoelectric PVDFmembranes have experienced a resurgence
of interest for energy harvesting. However, their use as electrical generators has remained
rather limited due to their relatively low power output, despite the large reversible elastic
deformation.
Starting from polarized PVDF film, we have shown that irradiation energy doses lower than
100 kGy is a competitive way to modify structural components of the PVDF, e.g, its elasticity,
without affecting the electro-active properties. The increase of crystallinity obtained for
range doses lower than 25 kGy could be exploited to enhance the piezoelectric response after
a further poling step. Moreover, the results suggest that irradiation doses higher than 25 kGy
reducing the crystallites size affecting the piezoelectric response. A homemade pressure-cell
system was realized to correlate the bending deformation on the PVDF membrane with
the output voltage. FT-IR, DSC and XRD techniques give new insights on which crystalline
part or structural change contributes at the surplus output voltage.
100 Presenter: G. Melilli IAEA–CN–241–443
A03
Chen Talk: Session A03, Monday 18:00 A03-06
Co-Reduction Synthesis of Graphene/Au Nanocomposite from
Graphene Oxide/Au3` Solution upon γ-Irradiation
J. Chen1, W. Liu1
1University of Science and Technology of China (USTC), Anhui Sheng, Hefei Shi, People’s Republic of China
Corresponding Author: J. Chen, jfchen@ustc.edu.cn
A simple method for reducing graphite oxide (GO) using γ-irradiation is explored without
using any photocatalysts or reducing agents. The obtained reduced graphene oxide (r-GO) is
investigated byXRD, TEMand FT-IR. Various spectroscopic and imaging techniques confirm
that most of the chemical functional groups present on GO are removed by irradiation,
and Au nanoparticles are deposited on r-GO sheets which prevents the aggregation of Au
nanoparticles. The nanoparticle size increases with increasing Au3` doping level. Moreover,
the catalytic activity of the r-GO/Au nanocomposites is also investigated.
IAEA–CN–241–164 101
A03
A03-07 Talk: Session A03, Monday 18:10 Othman
An Improved Method of Producing Adsorbent for Metal
Removal Using Radiation Induced Graft Polymerization
N. A. F. Othman1, Z. Ghazali1, T. A. Tuan Abdullah1, N. A. Shukri1, and
S. Selambakkannu1
1Malaysian Nuclear Agency, Bangi, 43000 Kajang, Selangor, Malaysia
Corresponding Author: N. A. F. Othman, nor_azillah@nuclearmalaysia.gov.my
Vapour phase grafting of kenaf fibre with glycidyl methacrylate (GMA) using radiation-
induced grafting was studied to develop an adsorbent for removal of metal from aqueous
solution. The preirradiation of kenaf fibre was carried out at different doses from electron
beam accelerator at various absorbed radiation doses (10 to 100 kGy). The grafting process
was carried out in a chemical vapour deposition reactor operated at temperature of 40˝C
and gauge pressure of 0 MPa to ´0.1 MPa with time range of 15 to 90 minutes. The
percentage of grafting, Pg (%) was calculated based on quantitative Fourier transform
infra-red spectroscopy (FTIR) analysis. The grafted fibre were confirmed using FTIR and
scanning electron microscopy. The optimal condition for enhancing Pg was obtained at
irradiation dose of 50 kGy, ´0.025 MPa gauge pressure, and temperature and reaction time
of 40˝C and 30 minutes, respectively. Optimization of these parameters will be a guide for
subsequent development of grafted copolymer for further functionalization for preparation
of adsorbent. The effect in thermal stability of polymeric material after the incorporation of
GMA was also investigated. It was found that incorporation of GMA increased the thermal
stability of kenaf fibre. The adsorption capacity was assessed to evaluate the efficiency of
the adsorbent towards aluminium removal. It was found that the adsorbent could remove
more than 99% aluminium with the highest adsorption capacity of 4.98 mg/g.
102 IAEA–CN–241–003
A03
Luo Talk: Session A03, Monday 18:20 A03-08
Fabric Modification by Radiation Methods
V. Luo1
1Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai Shi, People’s Republic of China
Corresponding Author: V. Luo, vincentluo@cgndasheng.com
Our research groups is devoted to develop fabric modification by radiation methods, espe-
cially by radiation induced graft polymerization of functional monomers or together with
nanoparticles.
The first research routine is based on radiation induced graft polymerization of the vinyl
monomers. As a first step, by grafting the functional acrylate or methacrylate we can
prepare superhydrophobic cotton fabrics which are durable for laundering and friction.
Furthermore, by grafting and then amination or amidoxination we can prepare the metal ion
exchangeable fabric for gold adsorption and reduction or uranium extraction from seawater.
The second research routine is based on radiation induced co-graft polymerization of
the vinyl monomers and the inorganic nanoparticles, for example, functionalized TiO2
nanoparticles or graphene oxide.
Very recently, we combined the radiation induced graft polymerization with the radiation in-
duced reduction, which resulted in an antibacterial cotton fabrics grafted with pomegranate-
shaped polymer wrapped in silver nanoparticle aggregations. This pomegranate-shaped
silver NPAs functionalized cotton fabric exhibits outstanding antibacterial activities and also
excellent laundering durability, where it can inactivate higher than 90% of both E. coli and
S. aureus even after 50 accelerated laundering cycles, which is equivalent to 250 commercial
or domestic laundering cycles.
The most advantage of the radiation methods in fabric modification is lying in the formation
of the covalent bonds between the cellulous macromolecules and the graft chains or together
with the nanoparticles, which is the key point for the laundering durability and permanent
functionalization.
IAEA–CN–241–094 103
A03
ICARST–2017
A04:Radiation for Environmental Protection I
104
A04
Takács Talk: Session A04, Tuesday 09:00 A04-01
Ionizing Radiation Induced Decomposition of Antibiotics in
Waste Water
E. Takács1
1Centre for Energy Research, Hungarian Academy of Sciences, Budapest, Hungary
Corresponding Author: E. Takács, erzsebet.takacs@energia.mta.hu
Wide varieties of toxic organic compounds are entering the aquatic environment. The main
sources of these impurities are the waste water treatment plants for domestic sewage. The
co-occurrence of sublethal antibiotic concentration and high density of microbial population
provides ideal condition for facilitating the selection and propagation of resistant bacteria in
sewage treatment plants. To reduce the amount of harmful organic compounds entering into
the receiving bodies of waste water a family of new technologies with the name advanced
oxidation processes (AOP) is under development. In these technologies highly reactive,
oxidizing radical intermediates (mainly OH radicals) are produced by various techniques,
e.g., by ionizing radiation. Radiolysis provides the benefit to produce reactive oxidizing
(‚OH and H2O2) and reduce (O‚2, e´aq and ‚H) species (or from a kinetic point of view highly
reactive electrophile and nucleophile species) in situ from water.
Electron pulse radiolysis experiments were conducted using a Tesla Linac LPR-4 accelerator
with kinetic spectrophotometric detection. A 60Co facility with 11.5 kGy/h dose rate was
used for γ-irradiation. LC/ESI-MS was used for final product analysis. The samples were
also characterized by COD, TOC, TN and pH measurements and by complex toxicological
analysis.
The oxidative and reductive decomposition of penicillin derivatives was studied, the change
in the antimicrobial activity of the drugs was followed. The reaction mechanism of ‚OH
induced oxidation of penicillins indicates the existence of a short-living and a stabilized
long-living ‚OH adduct to the sulfur. The e´aq is accommodated on the carbonyl groups of
the penicillin skeleton yielding ketyl radicals. Penicillins react with the hydrated electron
somewhat similarly to a tripeptide. It appeared that excessive or insufficient absorbed dose
is deleterious in relation to elimination of antibacterial activity. At low radical exposure the
forming products exhibit enhanced toxicity and antimicrobial potency. The adverse effect
at high radical exposure presumably arises from the forming polyhydroxylated phenolic
compounds.
The ‚OH induced decomposition of sulfonamide antibiotics in dilute solutions was also
studied by a wide variety of analytical techniques. The degradation was shown to start
with ‚OH addition to the aromatic ring, the cyclohexadienyl type radical thus formed reacts
with dissolved oxygen transforming to peroxy radical. This radical yields hydroxylated
molecules by HO‚2 elimination, or it undergoes ring opening to aliphatic compounds.
It was shown that e´ ‚aq and OH are able to demolish the penicillin’s β-lactam system re-
sponsible for their antimicrobial activity. However, careful optimization of the advanced
oxidation process, determination of the dose necessary for decreasing the toxicity and
improving the biodegradability is necessary. Based on complex investigations for both types
of antibiotics the degradation with the formation of inorganic ions is multistep process, the
molecules first are step-by-step oxidized and then mineralized.
IAEA–CN–241–370 105
A04
A04-02 Talk: Session A04, Tuesday 09:20 Wang
Ionizing Irradiation-Induced Degradation of PPCPs in Aqueous
Solution
J. Wang1, L. Chu1
1Tsinghua University, Haidian, Beijing, People’s Republic of China
Corresponding Author: J. Wang, wangjl@tsinghua.edu.cn
Pharmaceutical and personal care products (PPCPs), especially the pharmaceutically active
compounds (PhACs) such as antibiotics and hormones have attracted great concerns world-
wide for their persistence and potential threat to ecosystem and public health. PPCPs are
being increasingly detected only recently and considered as potential hazardous to ecosys-
tems owing to the rapid development of analytical techniques which enable quantifying
PPCPs at trace levels and investigating their fate and transformation pathways.
Ionizing irradiation is a promising alternative for degradation of PPCPs in aqueous solution.
The studies reviewed have demonstrated that ionizing irradiation effectively degrades a
wide range of PPCPs in aqueous solution. Many PPCPs such as antibiotics and X-ray contrast
agent could be removed completely by radiation. Solution pH is a key factor affecting PPCPs
degradation. However, high doses are needed for mineralization and toxicity reduction.
Development of the combined processes of ionizing irradiation with other techniques such
as H2O2 and ozonation would be a solution to increase the rate of mineralization and reduce
the cost.
In most cases, ‚OH radicals are the major reactive species responsible for the degradation
of PPCPs by irradiation. Identification of the intermediate and end products, addition of
a radical scavenger and the application of pulse radiolysis technique are the most tested
methodologies to explore the reaction mechanism of radiation-induced degradation and
optimize the degradation efficiency.
The majority of studies on PPCPs removal using ionizing irradiation have been orientated
towards the treatment performance and effects of operational parameters in pure water
solution. Moreover, high concentrations of PPCPs were used in most studies for detecting
those compounds easily, which can only reflect some situations such as the treatment of
industrial pharmaceutical effluent and are far from the real situation in water matrix. From
a practical point of view, studies on the decontamination and disinfection of the real effluent
or water containing PPCPs by ionizing irradiation should be paid more attention and the
transformation byproducts are of concern owing to their potential stability and toxicity.
The bioluminescence inhibition assay with Vibrio fischeri has been used to evaluate the
toxicological effect of PPCPs in aqueous solution after ionizing irradiation. Research on the
toxic evaluation of parent compounds and their degradation byproducts using a variety of
methods are needed in future studies.
106 IAEA–CN–241–087
A04
Pillai Talk: Session A04, Tuesday 09:40 A04-03
Efficacy of Electron Beam Irradiation to Address Emerging
Microbial Contaminants in Water Reuse Programmes
S. Pillai1, B. Batchelor2
1National Center for Electron Beam Research, College Station, TX 77845, USA
2Texas A&M University, College Station, TX 77840, USA
Corresponding Author: S. Pillai, s-pillai@tamu.edu
Water availability is a major challenge facing municipalities around the world. To meet
growing residential and agricultural needs, there aremajor water reuse programmes around
the world. These reuse programmes span all the way from indirect potable reuse to di-
rect potable reuse. The underlying hypothesis was that EB technology can breakdown
the emerging contaminants of concern in water reclamation and reuse projects. We also
hypothesized that the inactivation and elimination of contaminants by EB technology can be
achieved cost-effectively. Having this technology in the “tool-box” of water reclamation tech-
nologies would open up innovative high-value, commercially-viable, and environmentally
sustainable solutions and strategies for water reuse.
High energy electron beam irradiation was found to be effective in eliminating a variety of
emerging microbial contaminants such as hepatitis A virus, norovirus, rotavirus as well
as protozoa such as Cryptosporidium parvum. Additionally, EB was effective at achieving
significant reductions of bacterial pathogens such as Shigella spp., Aeromonas spp., and
Salmonella spp. Based on these studies, it was found that viral pathogens are the most
resistant to EB irradiation and protozoan oocysts were the most sensitive. If 5 kGy EB is
used for water reuse programmes, greater than 50-log reduction of bacterial and protozoan
pathogens can be achieved. The log reduction of viral pathogens however was significantly
lower ranging between 1 and 3 logs. These results suggest that EB irradiation technology
can be major cost saving for water reuse programmes since it avoids the needs for other
disinfection treatments and expensivemembrane filters (to remove pathogens). The outcome
of these analysis indicated that for large municipalities that require effluent treatment in the
hundreds of millions of gallons per day, the minimum power requirement is at least 1 MW.
Presently, commercial off-the-shelf (COTS) EB technology is available at significantly lower
power ratings.
IAEA–CN–241–229 107
A04
A04-04 Talk: Session A04, Tuesday 10:00 Borrely
Toxicity Assays Applications for Assessing Acute Effects for
Radiation Decomposition of Organics in Waters
S. Borrely1, D. Fungaro1
1Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), São Paulo, Brazil
Corresponding Author: S. Borrely, sborrely@ipen.br
The knowledge for using electron bem irradiation for pollutants degradation is developing.
Textile effluents and pharmaceuticals were the samples submitted to irradiations and to
acute toxicity assays. An electron beam accelerator was the radiation source used for the
treatment in batch experiments. Dafnids, rotifers and bacteria were applied for toxicity
measurements. All the assays were performed at LEBA/IPEN (Environmental Biological
Assays Laboratory). Doses required for decomposition of organics in water and related
toxicity indicated that reduced colour of effluents with 2.5 kGy and 5 kGy. These doses
were also suitable for toxic effects removal at pharmaceutical solutions (fluoxetine in sewage;
propranolol and fluoxetine mixture and at fluoxetine and voltaren mixture). Part of real
textile effluent (about 35% of samples) were very toxic (CE50 ă 5%) for daphnids and
luminescence Vibrio fischeri. The surfactants contained at textile effluent were the most toxic
compound. Vibrio fischeri luminescence was confirmed as one of the most sensitive assay,
followed by Ceriodaphnia dubia, Brachionus plicatis rotifers and Daphnia similis.
108 IAEA–CN–241–362
A04
Sun Talk: Session A04, Tuesday 10:20 A04-05
Radiation Technology Application in Environmental Protection
Y. Sun1, A. G. Chmielewski1
1Institute of Nuclear Chemistry and Technology (INCT), Warsaw, Poland
Corresponding Author: Y. Sun, y.sun@ichtj.waw.pl
Nitrogen oxides (NOx), sulfur dioxide (SO2), volatile organic pollutants (VOCs), polyaro-
matic hydrocarbons (PAHs) and dioxins are still main air pollutants. They aremostly formed
during fossil fuels combustion, solid waste incineration or at other industrial processes. In
recent years, cargo ships are the major emission source of SO2 and NOx emission generating
very high concentrations of these pollutants in off gases.
Electron beam (EB) flue gas treatment technology for purification of gaseous effluents from
coal fired boilers after testing in Japan, US, Germany, Poland, China and Bulgaria has been
implemented in industrial scale in Pomorzany Power Plant, Szczecin, Poland. It is a dry
scrubbing process with ammonia addition, high removal efficiency of SO2 (ą90%) and NOx
(ą70%) were obtained at 8 kGy absorbed dose, benign products were formed. EBFGT is
also a very promising technology to remove SO2 and NOx from flue gas generated by oil
fired burner plants what was demonstrated at the pilot test carried out in Saudi Arabian
oil refinery plant using a mobile accelerator. High removal efficiency of SO2 can be easily
achieved at low dose, however it needs very high dose (i.e., high energy consumption) to
obtain high removal efficiency of NOx. EB technology combined with catalyst to increase
removal efficiency of NO emitted from stationary source was investigated through computer
modelling simulations. The feasibility to remove SO2 and NOx from off gases generated
from cargo ship by using EB technology was investigated, preliminary results showed that
EB technology might be used to remove SO2 and NOx from off gases emitted from cargo
ship with presence of wet scrubbers instead of ammonia addition. NOx removal efficiency
was increased from 3% (EB only) up to 62% (EB combined with 4.5% salty water scrubbers)
at 8.8 kGy absorbed dose at 90˝C for the initial concentration of NOx being 1500 ppmv
with 500 ppmv SO2 presence. EB technology might be used for PAHs and other organic
pollutants removal as well. Recently emerging organic pollutants have been detected in
tap water or ground water, their persistence cause people’s concern. ICHTJ researchers
have studied perfluorinated organic compounds (perfluoctanoic acid as a representative
compound) destruction in aqueous solution by using EB or γ-irradiation. It showed that
more than 80% PFOA was decomposed at 5 kGy dose under γ-ray irradiation in argon-
saturated solution of pH 2.0 containing 20 mg/` of t-butanol for initial concentration of
PFOA being 1 mg/`; under EB irradiation, nearly 100% PFOA was decomposed at 105 kGy
dose. In order to get better understanding decomposition mechanism of PFOA under EB
irradiation, a computer simulation was carried out. Good agreement was obtained between
calculation and experimental results.
IAEA–CN–241–212 109
A04
ICARST–2017
A05:Advances in Radiation Chemistry Research I
110
A05
Wojnárovits Talk: Session A05, Tuesday 11:15 A05-01
Basic Radical Reactions in Water Treatment by Ionizing
Radiation
L. Wojnárovits1
1Centre for Energy Research, Hungarian Academy of Sciences, Budapest, Hungary
Corresponding Author: L. Wojnárovits, wojnarovits.laszlo@energia.mta.hu
In the so-called advanced oxidation processes (AOP) and in water treatment by ionizing
radiation, which belongs to the class of AOP’s, too, the main goal is to destroy, or at least to
deactivate harmful water contaminants: pharmaceuticals, pesticides, surfactants, health-
care products, etc. The chemical transformations are suggested to be initiated by hydroxyl
radicals. However, some other inorganic radicals may also contribute to initiating the
degradation.
The changes due to irradiationwere followed by taking the UV-Vis spectra and bymeasuring
the chemical oxygen demand (COD) before and after irradiation. The degradation products
were identified after LC separation with MS-MS detection. To obtain information about
the degradation, kinetics pulse radiolysis with kinetic spectroscopic detection was used.
The spectra of the intermediates were calculated from the kinetic curves (radical concentra-
tion versus time, on the µs time scale) taken at different wavelengths. These spectra give
information about the structure of the intermediates.
The kinetics and reaction mechanisms of a large variety of inorganic radicals with organic
molecules were studied. It was shown that other inorganic radicals as ‚OH also contribute
highly to the initiation of degradation in most AOP’s. Cl´ and HCO´3 in the treated water
reacting with ‚OH transform to the Cl‚´2 and CO
‚´
3 oxidizing. Reactions of e´aq andH‚ water
radiolysis intermediates may also contribute to the degradation. In the primary reactions
of all these radicals with organic molecules, carbon-centred radicals are produced. The
reactions of the carbon-centred radicals with dissolved oxygen (DO) basically determine
the oxidation rate. The peroxy radicals formed in the reactions of aliphatic carbon-centred
radicals with DO may transform to peroxides and hydroperoxides, with the intervention
of these intermediates gradual degradation takes place. Aromatic carbon-centred radicals
(cyclohexadienyl radicals) in reversible processes react with DO, where the ring degradation
is suggested to take place from the aromatic peroxi radicals. The primary carbon-centred
radicals in uni- or bi-molecular processes may transform to other, e.g., oxygen or nitrogen
centred radicals. These intermediates (e.g., phenoxy or anilino radicals) do not react with
DO. Therefore, the initial degradation rate is low when, during the degradation reactions,
there is a possibility for the formation of these radicals.
The carbon-centred radical formed in the reaction of a one-electron oxidizing radical with
an organic molecule undergoes a second oxidation step when it reacts with DO. This
reaction may be followed by further oxidations starting from the peroxy radical thus formed,
or from the peroxide/hydroperoxide stabilization products. These reactions increase the
degradation efficiency with a result that the one-electron oxidants induce 2–4 electron
oxidations. When the radical does not react with DO, the degradation rate is low.
IAEA–CN–241–388 111
A05
A05-02 Talk: Session A05, Tuesday 11:35 Al-Sheikhly
Synthesis of Novel Fabrics for Extraction of Uranium from
Seawater
M. Al-Sheikhly1
1University of Maryland, College Park, MD 20742, USA
Corresponding Author: M. Al-Sheikhly, mohamad@umd.edu
The world’s oceans contain more than 4.5 billion tons of uranium; however, access to this
resource is limited by the ability to extract uranium from seawater efficiently. Lacing fabric
substrates with chemical functionalities specific for uranium adsorption is one approach to
meeting this challenge. Advanced adsorbent materials are being developed using polymeric
substrates with high chemical stability, excellent degradation resistance and improved
mechanical properties. Fabrics include polypropylene, nylon and advanced Winged Fibres
fromAllasso industries featuring extremely high surface areas for improved grafting density.
Using a 60Co γ-source and 10–32 MeV electron beam linear accelerator, the various fabrics
have been irradiated over a wide range of dose rates, total doses and temperatures.
Innovative vinyl phosphate and oxalate exhibiting high distribution coefficients and se-
lectivity for uranium along with excellent potential for free radical polymerization have
been utilized in the functionalization of the fabric substrates. Azo compounds with higher
selectivity have also been utilized but have required the use of a grafted chemical precursor.
Attachment of the chelating adsorbent or its precursor to the substrate polymer ismaximized
through the optimization of numerous variables including monomer concentration, dose
rate, total dose, solvent and temperature.
Following irradiation, fabrics are washed, dried and weighed to determine the degree of
grafting (DoG). The presence of monomer in the fabrics is verified using numerous exper-
imental techniques including X-ray photoelectron spectroscopy (XPS), scanning electron
microscopy-energy dispersive spectroscopy (SEM-EDS), and Fourier-transform infrared
spectroscopy-attenuated total reflectance (FTIR-ATR). Zeta potential measurements allow
for surface charge measurements to confirm the negative charge required for uranium chela-
tion. The fabric capacity for uranium extraction was tested by rotating samples for 7 days in
a rotary agitator with actual seawater spiked with 0.2 or 1.0 mg{` uranium. The fraction of
uranium in the solution which was removed due to uptake on the fabrics was found to rise
with increasing DoG at both uranium concentrations. SEM-EDS measurements are used to
map the distribution of adsorbed uranium on the polymeric fibres.
Current work includes optimization of grafting density in addition to material characteriza-
tion on the molecular level and analysis of the sample microstructure. Further testing in
synthetic seawater will be conducted to compare the selectivity of each adsorbent fabric
towards uranium compared to that of other species, in addition to determining the loading
and adsorption rates under various conditions such as pH, temperature and salt concen-
tration. Experiments in real seawater will consider effects of organics on the adsorbent
materials, test for durability and reusability and determine kinetics and efficiency of the
uranium extraction as a function of degradation.
112 IAEA–CN–241–419
A05
Mostafavi Talk: Session A05, Tuesday 11:55 A05-03
Ultrafast Electron Transfer Studied by Picosecond Pulse
Radiolysis
M. Mostafavi1
1Université Paris-sud, 91400 Orsay, France
Corresponding Author: M. Mostafavi, mehran.mostafavi@u-psud.fr
Furthering our knowledge on the reactivity of short-lived species in irradiated water at ul-
trafast timescales is necessary to understand the competitive reactions occurring within the
first ps. The composition of aqueous solutions and the water/solid interface can potentially
favour or inhibit one of these competitive ultrafast processes, such as electron hydration,
electron hole recombination, proton transfer, or oxido-reduction of the solute. Pulse radiol-
ysis measurements with 7 ps time resolution show that ultrafast electron processes occur in
highly concentrated aqueous solution. The reactivity’s of presolvated electron, pre-OH‚
radical and pre-H‚ atom radical are examined. By measuring the yield of the transient
radical after the pulse it is shown that H ‚`2O radical undergoes an electron transfer and
presolvated electron and pre-H‚ atom are very efficient reducing species.
IAEA–CN–241–291 113
A05
A05-04 Talk: Session A05, Tuesday 12:15 Dubois-Clochard
Advances in Etched Ion-Track Polymer Membranes for
Environmental and Microelectronic Applications
M.-C. Dubois-Clochard1
1Laboratoire des Solides Irradiés (LSI/CEA), École Polytechnique, 91128 Palaiseau, France
Corresponding Author: M.-C. Dubois-Clochard, marie-claude.clochard@polytechnique.edu
Etched ion-tracks membranes are well-known and commercially available membranes
for filtration which have, in the past decades, attracted a huge interest for applications in
life sciences. More recently, since these membranes serve as template for nanowires or
nanotubes fabrication, applications in microelectronics (e.g., MRAM for computers) have
also been widely investigated. Control over the swift heavy-ion irradiation and subsequent
etching condition enables the production of multiple or single channels of high aspect ratio.
Playing on polymers chemical structure, crystallinity and track-etching strategies, channels
of predefined sizes and geometries can be tuned such as cylindrical, conical or oblade-
shaped channels, crossed-channels and so on. These track-etching technique presents the
advantage to be industrially scalable. Among other examples, we will discuss how a large
area fabrication of self-standing nanoporous graphene-on-PMMA substrate (interesting
candidates for field-emission transistors) can be achieved simply.
Ten years ago, we have shown that, after a relatively short etching time, some track-etched
nanoporous polymermembranes exhibited an EPR signal witnessing the presence of remain-
ing radicals. These radicals, results of ion-matter interactions from previous irradiation,
have been found reactive enough to initiate the radiografting of vinyl monomers. The
grafted polymer chains are specifically localized on and all along the nanopores walls. This
discovery has opened our applications field from polymer electrolyte membranes for fuel
cells to the development of sensors of pollutants in waters.
In this talk, we will present our very recent achievements on etched ion-track polymer mem-
branes for sensor applications in environment andmicroelectronics. The key of success is the
use of a peculiar polymer, the poly(vinylidene difluoride) (PVDF). PVDF is a biocompatible
and semi-crystalline polymer. Depending its crystallinity phase, it can also be piezoelectric.
We will present how we have exploiting these properties for sensor applications.
114 IAEA–CN–241–442
A05
Goldstein Talk: Session A05, Tuesday 12:35 A05-05
Using Ionizing Radiation for Studying Radical Reactions with
Nitroxides: Implications for their Biological Activity
S. Goldstein1
1Institute of Chemistry, Hebrew University of Jerusalem, Jerusalem 9190401, Israel
Corresponding Author: S. Goldstein, sara.goldstein1@mail.huji.ac.il
Radicals are part of the chemistry of life. The ever-increasing knowledge of the involvement
of radicals in diverse pathological processes has expanded the search for more efficient
antioxidants that can diminish radical-induced damage. Stable nitroxide radicals are re-
ceiving increased attention as potential therapeutic agents because of their pronounced
antioxidative activity, low toxicity, and attenuation of oxidative and nitrosative damage
in vitro and in animal models of inflammatory diseases.
We have used ionizing radiation for elucidating the kinetics and mechanisms of nitrox-
ides reactions with radicals as well as with reduced metal ions and semiquinone radicals.
Radicals which are neither good oxidants nor reductants such as carbon-centred radicals
generally add to the nitroxyl group forming relatively stable adducts. The reactions of ‚NO2,
HO‚2 and peroxyl and thiyl radicals with nitroxides proceed via an inner-sphere electron
transfer mechanism. The reactivity of nitroxides towards most radicals, excluding HO‚2
and peroxyl radicals, hardly depend on their structure. In the case of HO‚2ppKa “ 4.8q the
nitroxides reactivity decreases as the pH increases and, therefore, at physiological pH they
are poor SOD-mimics.
The rate constant of nitroxides reaction with ‚NO2 is extremely high (7ˆ 108 M´1s´1), and
nitroxides catalytically prevent protein nitration, which is involved in diverse pathological
processes. This has been demonstrated in vitro during the peroxidative activity of heme
proteins in the presence of H2O2 and nitrite and in vivo using a mouse model of allergic
asthma, which is an inflammatory disease, reflected by increased production of reactive
oxygen and nitrogen species. The protective effects of nitroxides in suppressing the increase
of main asthmatic inflammatory markers substantiate the key role played by reactive oxygen
and nitrogen species in the molecular mechanism of asthma. Nitroxides are superior over
common antioxidants, which their reaction with radicals always yields secondary radicals
leading eventually to consumption of the antioxidant. Nitroxides act catalytically since
their reactions with radicals form the respective oxoammonium cations, which are readily
reduced back to the parent nitroxides by biological reductants.
The effects of the nitroxides are instrumental not only in protecting against oxidative and
nitrosative damage, but also in elucidating the mechanisms underlying these processes.
IAEA–CN–241–447 115
A05
A05-06 Talk: Session A05, Tuesday 12:55 Barilla
Influence of N2O and Ethanol on the Chemical Stage of
Radiobiological Mechanism
J. Barilla1, M. V. Lokajícek2, H. Pisakova2, and P. Simr1
1Jan Evangelista Purkyně University in Ústí nad Labem, Czech Republic
2Institute of Physics, Academy of Sciences of the Czech Republic, Praha, Czech Republic
Corresponding Author: J. Barilla, jiri.barilla@ujep.cz
The biological effect of ionizing radiation may be rather strongly influenced by the presence
of other substances in the corresponding medium during irradiation; see the problem of
oxygen effect in tumor radiotherapy (at lower LET values). The radicals HO2 arising in
diffusing radical clusters formed mainly by densely ionizing ends of secondary electrons
are responsible for the enhanced effect in damages of DNA molecules. Their frequency in
the dependence on oxygen concentration will be presented, having been established with
the help of our model based on the use of Petri nets. There are, of course, other substances
(radiosensitive as well as radioprotective) that may influence the radiobiological effect and
be practically applied too. We have chosen two of them: N2O and ethanol (acting in opposite
ways). Molecules N2O react with hydrated electrons to form OH radicals which increase
DNA damage while ethanol acts as scavenger of radicals and lowers DNAmolecule damage.
To create the mathematical model which describes physical and chemical processes in the
chemical stage of radiobiological mechanism we have used Continuous Petri nets. It enables
us to describe and study the influence of both themain parallel processes: chemical reactions
and diffusion of radical clusters. It is possible to study the time change of concentration
of individual radicals during this diffusion process, which may be very helpful when the
efficiency of different substances present in medium in the DNA damage (radiobiological
effect) is to be studied. Concurrently, Petri nets enable us to simulate dependences of
radical concentrations on concentration of oxygen, N2O and ethanol which may be very
helpful to study influences of those substances on DNA damage and find out their optimal
concentration for radiotherapy and protection of cells against ionization radiation. We have
started to study the corresponding problem earlier with the help of analytical model where
system of differential equations has been used. The given model has been applied to the
experimental data obtained for 60Co radiation. The results of this model have been used for
setting of basic parameters of Petri nets model.
116 IAEA–CN–241–069
A05
Marzouki Talk: Session A05, Tuesday 13:05 A05-07
EPR Characterization of γ-Irradiated Xerogels
K. Marzouki1, H. Ben Ouada2
1National Center for Nuclear Sciences and Technologies (CNSTN), Sidi Thabet, Tunisia
2Faculté des Sciences de Monastir, Monastir, Tunisia
Corresponding Author: K. Marzouki, kaouther.marzougui@cnstn.rnrt.tn
Silicate glass was considered as suitable material for dosimetric purposes, and the study
of stable paramagnetic centres induced by radiation has proven its potential for radia-
tion dosimetry. Despite its several advantages that make it especially attractive, silicate
presents some disadvantages like heterogeneity of chemical composition and high melting
temperature. These problems can be resolved by elaboration of silica glass at room tempera-
ture via sol-gel method, which was an excellent and economically process offering purity,
homogeneity besides to control components and properties of this material.
In this study, the sol gel process preparation starts from a solution containing tetraethoxysi-
lane (TEOS) precursor and consist mainly on two steps, hydrolysis and polycondensation.
Hence, the sol to rigid glass conversion took place after loss of solvent, with drying gels at
room temperatures and then γ-irradiated in order to induce paramagnetic centres. Therefore,
we report in this study, the paramagnetic states induced after irradiation in iron doped and
pure SiO2 sol-gel glasses. The aim of the present work is to investigate the EPR properties
of sol-gel silica glass and to ascertain its possible use for high dose dosimetry.
The EPR spectra of unirradiated silica, recorded at room temperature and at 140K exhibit a
silent spectrum. However, major changes occur in the spectra of γ-irradiated samples are
attributed to the formation of non-bridging oxygen hole centres and E’ centres. The spectrum
of iron doped silica recorded at 140K consists of four resonances: g “ 4.3 attributed to ion
Fe3`, g “ 8.27 and g “ 2.73 associated to presence of iron clusters in pores, finally g “ 1.99
may be due to defects of irradiation in sol-gel material.
The preliminary EPR analysis of radiation induced paramagnetic centres in sol-gel silica rep-
resents a relevant approach to dosimetry. According to the current results, complementary
AFM and FTIR studies are in progress.
IAEA–CN–241–331 117
A05
ICARST–2017
A06:Dosimetry and Standards for Radiation
Processing
118
A06
Kovács Talk: Session A06, Tuesday 14:15 A06-01
Process Control Methods in Radiation Technologies
A. Kovács1
1Atomic Energy Engineering Co. Ltd., Hungary
Corresponding Author: A. Kovács, akovacs.iki@gmail.com
Radiation processing has become a well-known and well-accepted technology worldwide
using different type γ-irradiation facilities, electron accelerators and X-ray machines. The
technology is applied at various fields like radiation sterilization of medical devices, man-
ufacturing of polymer products used in industry and health care, irradiation of various
food and agricultural products, as well as the emerging technologies like synthesis of ad-
vanced materials and environmental protection. The successful implementation of these
technologies depends very much on reliable quality assurance, i.e., the measurement of
absorbed dose during process validation and control, the continuous check of machine
parameters and the use of mathematical modelling in certain stages of the technology. It is
achieved by using harmonized and standardized dosimetry procedures performed with dif-
ferent type and category product specific dosimetry systems. Dosimetry, as part of the total
quality system provides quality assurance and documentation that the irradiation process
was performed according to the preset specifications. Accurate and traceable dosimetry
measurements, based on suitable calibration procedures, provide independent means for
quality control in radiation processing.
In all validation steps (as described in ISO Standard 11137), i.e., during process definition,
installation, operational and performance qualification, as well as in routine process control,
various reference standard and routine dosimetry systems are applied for quality control.
In the course of the presentation the main dosimetry procedures, required during the
validation steps will be discussed. Thus the selection and use of reference and routine
dosimeters for the characterization of the irradiation facility and the establishing of the
irradiation technology as well as for routine process control will be highlighted through
practical examples. Besides the challenges and solutions relevant to different irradiation
facility designs and recent radiation technology requirements will be shown with respect to
available process control methods.
IAEA–CN–241–404 119
A06
A06-02 Talk: Session A06, Tuesday 14:35 Miller
Dosimetry and Process Control for Using Low Energy Electron
Beams for Sterilization or Decontamination of Surfaces
A. Miller1,M. Bailey2
1DTU Nutech, Technical University of Denmark (DTU), Denmark
2Risø High Dose Reference Laboratory, Risø, Denmark
Corresponding Author: A. Miller, armi@dtu.dk
Low energy electron beams (100–200 keV) are used for sterilization or microbiological
decontamination of surfaces in the medical device and pharmaceutical industry. This
paper describes dosimetry methods used for validation and routine process control of these
processes.
Dosimetry methods employed in high energy EB or γ-sterilization cannot be used at low
energy EB, where the accelerated electrons are stopped within the dosimeter, and special
methodology has been developed for this purpose. It is described how measurement
traceability is maintained for dose measurement at low energy electron irradiation, and an
uncertainty budget is also developed and described.
The basis for establishing a maximum acceptable dose and a dose needed for an effective
process is given as well.
120 Presenter: M. Bailey IAEA–CN–241–395
A06
Kuntz Talk: Session A06, Tuesday 14:55 A06-03
Is IQ/OQ/PQ Part of Irradiation Process Control?
F. Kuntz1, E. Pawlak2
1Aérial CRT, Illkirch-Graffenstaden, France
2Conseil National des Employeurs d’avenir (CNEA), 94146 Alfortville Cedex, France
Corresponding Author: F. Kuntz, florent.kuntz@aerial-crt.com
Regulations and ISO standards applicable for medical devices require that validation of a
process shall be performed. In fact, both the U.S. Quality System Regulation 21 CFR Part 820
and ISO 13485:2012 have explicit elements requiring the manufacturer to perform tasks
associated with IQ, OQ and PQ.
Only after performing IQ, OQ and PQ successfully with a desired result and established
documents that verify each phase, can production get underway. This defined discipline for
process validation has proven to be the ideal way to guarantee the best quality production
and this, constantly over time.
During production, process control is the phase involved in ensuring the process is stable
and consistently operating at the target level of performance with variations which have
been set accordingly during OQ and PQ.
Relevant documents adapted to the radiation processing industry, such as ISO 11137-3,
ISO14470, ISO/ASTM51649, ISO/ASTM51702, ISO/ASTM51608, ISO/ASTM52303, AAMI/
TIR 29 describe the purpose and the experiments to be conducted during IQ, OQ and PQ
and routine control of the process of irradiation.
The purpose of this presentation is to show actual results of irradiation plant qualification
following the mentioned standards/guides and an approach for routine process control.
Preliminarily to those results, the dosimetry system calibration step and a dosemeasurement
inter comparison conducted within the RLA 1013 004 ARCAL project, will be addressed
since OQ/PQ results are mainly based on absorbed dose measurements.
IAEA–CN–241–346 121
A06
A06-04 Talk: Session A06, Tuesday 15:15 Zhang
Dosimetry Standards and Dissemination Systems for Radiation
Processing in China
Y. Zhang1, X. Xia1, X. Gong1, and J. Zhang1
1National Institute of Metrology (NIM), Chaoyang Dist, Beijing, People’s Republic of China
Corresponding Author: Y. Zhang, zhangyl@nim.ac.cn
In order to adapt the development of radiation processing and ensure that the product has
been treated with an acceptable range of absorbed doses in China, a programme of high
dose standardization was initialed in 1983. The high-dose standards and dissemination
system has been established at NIM. The ferrous sulfate (Fricke) dosimeter is accepted
as national reference standards, the ceric-cerous sulfate and potassium/silver dichromate
liquid chemical dosimeters and alnine/EPR dosimeter are selected as transfer standards at
NIM. The Fricke, potassium/silver dichromate, several kinds of radiochromic films (RCD),
cellulose triacetate (CTA) and polymethylmethacrylate (PMMA) dosimeters have been
recommended as routine dosimeters for radiation processing in China. A series of national
standards, verifications and technical norms have been enacted and issued on the dosimetry
for radiation processing and on the approval of irradiation facilities. This programme plays
an important role in the dose measurement standardization and product quality assurance
for radiation processing. This paper presents a brief overview of dosimetry activities for
radiation processing carried out at NIM during the last 10 years. Calibration of systems
with the Fricke reference standard and comparison of absorbed dose results obtained from
NDAS program with potassium/silver dichromate dosimeter and alnine/EPR dosimeter
for radiation processing in China are also discussed.
122 IAEA–CN–241–068
A06
Ebraheem Talk: Session A06, Tuesday 15:35 A06-05
EPR Dosimetry Systems; Assessment and Developed in NCRRT
S. Ebraheem1
1National Center for Radiation Research and Technology (NCRRT), Nasr City, Cairo, Egypt
Corresponding Author: S. Ebraheem, seif_dose@yahoo.com
During the last two decades, a team of NCRRT researchers developed and assisted many
dosimetry systems depending on the electron paramagnetic resonance (EPR) analyzing
method. EPR dosimetry is characterized by its non-destructive read-out and the possibility
of dose archival. Recently, monosodium glutamate powder and prepared rods containing
different concentration of it (3ˆ 10 mm) were studied to be a radiation sensitive dosimeter
measured by ESR method of analysis. The dose range from 10–90 kGy tested for powder,
whereas, rods are useful in the dose range from 10–120 kGy.
NCRRT researchers studied different substances evaluated as; taurine, strontium carbonate,
riboflavin, strontium carbonate, anhydrous strontium sulfate, 2-methylalanine, magnesium
lactate, ammonium oxalate, and arginine mono-hydrochloride. The response of taurine to γ-
radiation doses in the range from 0.1 to 50 kGy was investigated, as well as that in the range
from 1.0 to 20.0 Gy using numerically enhanced EPR taurine spectra. The radiation-induced
defects in strontium carbonate (SrCO3) rod dosimeter in the dose range of 2.5 Gy–25 kGy
was investigated using EPR resonance technique. The un-irradiated riboflavin (RF) exhibits
a very weak EPR signal (g “ 2.00950) and upon γ-ray exposure the signal increases up to
an absorbed dose of 50 kGy. Anhydrous strontium sulfate (SrSO4) has shown a promise
candidate as a dosimeter for low dose applications producing unique EPR signals with
γ-rays which it has a linear response relationship (r2 « 0.999) in the range of 1–100 Gy. The
dosimetric characteristics of γ-radiation induced free radicals in 2-methylalanine (2MA)
pellet dosimeter are investigated using EPR in the high-dose range of 1–100 kGy. The EPR
spectrum of irradiated magnesium lactate (ML) rods was characterized by a quartet signal
with the spectroscopic splitting g-factor of 2.0048700003 at 0.4 mT. The useful dose range
of the rod dosimeter was 100 Gy to 80 kGy. The dosimetric properties of the of ammonium
oxalate (COONH4)2H2O studied under low and high radiation doses. The EPR spectra of
ammonium oxalate have the spectroscopic splitting g-factor of 2.00095 for C2O´4 radical
detected as EPR signal. The dose-response curves have very good linearity in the range
10–1000 Gy for low doses and show slight sub-linearity in high dose region up to 25 kGy.
Arginine mono-hydrochloride rods (3–10 mm) were irradiated with 60Co γ-rays to study
radicals for dosimetric materials with EPR. The rods have significant signal which develops
upon irradiation and the intensity of signal increases upon the increase in irradiation dose,
in the dose range from 5 to 120 KGy.
More and more articles ware published by the NCRRT researchers group dialing with this
issue represents the unique analyzing method of using EPR in the field of dosimetry.
IAEA–CN–241–440 123
A06
ICARST–2017
A07:Advances in Radiation Chemistry Research II
124
A07
Feldman Talk: Session A07, Tuesday 16:30 A07-01
The Radiation Chemistry of Organized Systems: Basic Studies
and Implications
V. Feldman1
1Department of Chemistry, M. V. Lomonosov Moscow State University, Moscow, Russian Federation
Corresponding Author: V. Feldman, feldman@rc.chem.msu.ru
The development of new approaches to radiation stabilization and radiation processing
in various fields should be essentially based on consideration of the efficiency and spatial
selectivity of the radiation-induced events in complex molecular systems and polymers. In
fact, as shown in a number of recent studies, the radiation chemistry of such systems may
be controlled by rather subtle effects, e.g., molecular packing determined by relatively weak
interactions, conformation, supramolecular structure, dynamics on interfaces, etc. It implies
that, in addition to understanding the radiation-chemical processes at the molecular level,
one should consider the effect of system organization on the primary radiation-induced
processes and kinetics of postirradiation reactions.
This lecture will present an overview of the modern concept of radiation chemistry of
organized systems and illustrate its basic aspects and implications with results on different
systems (from the simplest intermolecular complexes to nanocompsites) obtained in our
laboratory during the past decade. Experimental characterization of the radiation-induced
effects and structural changes was carried out using various methods, including EPR,
UV/VIS, and FTIR spectroscopy, TEM and XRD analysis and complemented by theoretical
simulations, when applicable.
The illustrative examples briefly covered in this lecture will include i) radiation-chemical
transformations of frozen intermolecular complexes; ii) specific features of the radiation-
driven processes in room-temperature ionic liquids (RTIL); iii) mechanism of the radiation-
induced degradation of crown-ether based systems. Particular attention will be paid to
nanostructured systems. A new method of controlled single-stage radiation-chemical
synthesis of metal-polymer nanocomposites from the inter-polyelectrolyte complex films
developed in our laboratory will be presented. This method makes it possible to obtain the
composite films containingmetallic or bimetallic nanoparticles with various size distribution
and spatial organization using X-rays or fast electron beams. The results obtained with
X-ray irradiation of nanostructured systems demonstrated a prominent effect of “radiation-
chemical contrast” with possible applications for selective modification of nanocomposites
and targeted sensitization (e.g., in radiotherapy).
Finally, the implications of the radiation chemistry of organized systems for various existing
and emerging technologies (ranging from nuclear waste treatment to fabrication of new
nanomaterials and nanolithography) will be outlined.
IAEA–CN–241–349 125
A07
A07-02 Talk: Session A07, Tuesday 16:50 Jonsson
Interfacial Radiation Chemistry in Nuclear Technology
M. Jonsson1
1KTH Royal Institute of Technology, Stockholm, Sweden
Corresponding Author: M. Jonsson, matsj@kth.se
Radiation effects on materials constitute a unique and often crucial feature in the nuclear
industry. The effects can be either direct, due to radiation energy deposition in the mate-
rial, or indirect, due radiation energy deposition in the surrounding media subsequently
transferred to the material via chemical reactions. In the majority of nuclear technological
systems such as nuclear reactors, fuel reprocessing plants and geological repositories for
used nuclear fuel, the surrounding medium exposed to ionizing radiation is water. This is
one of the reasons why the radiation chemistry of aqueous solutions has been studied so
extensively. However, even though processes occurring in aqueous solutions are extremely
important, the most crucial processes from a practical point of view are those occurring at
the interface between the aqueous phase and solid materials as these can strongly influence
the performance and the integrity of the facility. Of particular concern are corrosion pro-
cesses induced by oxidative radiolysis products. In most cases the solid material of relevance
is metallic or ceramic (primarily UO2 in nuclear fuel). Hence, the surface of the material
is an oxide. It has been reported that the yields (G-values) of the radiolysis products can
change significantly in the vicinity of oxide surfaces. The rationale for this phenomenon
is still debated. In addition, oxide surfaces have been shown to catalyze several reactions
involving the molecular aqueous radiolysis products (H2, H2O2 and O2). Consequently, it is
of utmost importance to gain fundamental understanding of the radiation driven processes
of interfacial systems. In this paper, interfacial radiation chemistry will be discussed in
general and the reactions of molecular radiolysis products catalyzed by oxide surfaces in
more detail.
The oxide materials that have been studied are UO2, Cu2O and CuO of relevance in geo-
logical repositories for spent nuclear fuel according to the KBS-3 concept (copper coated
canister), ZrO2 of relevance in nuclear reactors (fuel cladding) and numerous other ox-
ides that were mainly studied in order to understand the influence of fundamental oxide
properties on the catalytic properties of the surface.
The experiments show that the catalytic decomposition of H2O2 yielding O2 and H2O as
final products proceed via the intermediate formation of surface bound hydroxyl radicals.
This process is catalyzed by most oxide surfaces. For irradiated systems it is also obvious
that radiolytically formed hydroxyl radicals adsorb to oxide surfaces present in the aqueous
phase. Specific studies of metallic copper in water have shown that copper irradiated in
anoxic aqueous solution undergoes significant corrosion and takes up more hydrogen than
copper exposed only to water during the same period. Other experiments reveal that H2
and O2 produce H2O2 at room temperature in aqueous solution containing oxide surfaces.
In conclusion, oxide surfaces catalyze a number of reactions that are usually not accounted
for in homogeneous aqueous radiation chemistry. The molecular radiolysis products yield
surface bound radicals of unknown stability. To fully understand present and future systems
of relevance in nuclear technology, wemust strengthen our knowledge in interfacial radiation
chemistry.
126 IAEA–CN–241–274
A07
Horak Talk: Session A07, Tuesday 17:10 A07-03
Radiation Sterilization of Devices and Scaffolds for Tissue
Engineering
C. I. Horak1
1Comisión Nacional de Energía Atómica, (CNEA), Buenos Aires, Argentina
Corresponding Author: C. I. Horak, celina.horak@gmail.com
A sterile medical device is one that is free of viable microorganisms. This can be achieved
through: a terminal sterilization process, sterilization of some components, a combination of
chemical/physical sterilization and aseptic processing. The choice of a sterilization process
and the sterility assurance level (SAL) should be addressed early in the development of
the product and process design requirements in conformance with an integrated quality
and risk assessment management system. For radiation sterilization, many standards are
proposed to validate the process, and the substantiation of this sterile claim over time is
through the dose audit process.
For the sterilization of all medical devices the most rigorous SAL (10-6SAL) should be
selected and used based upon the ability of the product to function after it undergoes the
sterilization process. But, many of the proposed scaffold materials do not withstand high
doses to reach a 10-6SAL; so a lower SAL should be investigated on a risk based assessment,
that involved the following criteria according the pretended use: Products intended to
come into contact with breached skin or compromised tissue; Invasive products that enter
normally sterile tissue; Products with claims of sterile fluid pathways; Surgically implanted
devices; Products not intended to come into contact with breached skin or compromised
tissue; Topical products that contact intact skin or mucous membranes, among others.
Sterilization by irradiation has shown a strong applicability for a wide range of products,
such as single-use medical devices, tissue-based devices, combination devices, implantable
devices and pharmaceuticals. Most of them are sensitive products, but, due to the new
standards approaches, radiation sterilization has proven itself to be an effective and flex-
ible method as indicated by its acceptance in the different pharmacopoeias and sanitary
authorities.
IAEA–CN–241–450 127
A07
A07-04 Talk: Session A07, Tuesday 17:30 El Naggar
Effect of Sterilization by γ-Irradiation on Biocompatibility of
Starch-Based Polymers and Composites Suitable for Stem Cell
Growth
A. W. El Naggar1, M. Senna1, S. Korraa1, and S. Refaay1
1National Center for Radiation Research and Technology (NCRRT), Nasr City, Cairo, Egypt
Corresponding Author: A. W. El Naggar, skpaems@yahoo.com
Studies with biodegradable starch-based polymers have recently demonstrated that these
materials have a wide range of properties, which make them suitable for use in several
biomedical applications, ranging from bone plates and screws to drug delivery carriers and
tissue engineering scaffolds. A novel non-toxic biodegradable starch based polymer was
developed for use in tissue engineering applications. The starch and its blends consisted
of: 100% starch; starch mixed with 10% cellulose acetate, 10% acrylic acid and 5% carboxy
methyle cellulose; and starch mixed with 10% cellulose acetate and 10% carboxy methyle
cellulose. Scaffolds were sterilized by ionizing radiation and cells were allowed to grow
on the designed scaffolds. Biocompatibility evaluation of such blends was carried out
using Hep-2 cells, which were cultured in direct contact with the different starch blends
for 72 hours and observed in light and scanning electron microscopy (SEM). Viability was
assessed using the light microscope, DNA content, nitric oxide content, lipid perocidation
and MTT assay. Also, the effect of low level laser energy (LLLI) on enhancing the prolifera-
tion of cells on such scaffolds, were examined, where cells were exposed to He:Ne laser at
doses 1, 2.5 and 5 J/cm2 every daily for a duration of two days. Both types of starch-based
polymers exhibit biocompatibility that can allow for their use as biomaterials. Starch mixed
with 10% cellulose acetate and 10% carboxy methyle cellulose blends were found to be the
less cytotoxic for the tested cell line, although cells adhere better to starch cellulose acetate
surface. Exposure to 2 J/cm2 He:Ne laser greatly enhanced cell proliferation on all of the
given scaffolds.
128 Presenter: S. Korraa IAEA–CN–241–343
A07
Kavirayani Talk: Session A07, Tuesday 17:50 A07-05
Radiation Chemical Studies Leading to the Development of
Selenium Radioprotectors
I. P. Kavirayani1
1Bhabha Atomic Research Centre (BARC), Mumbai, India
Corresponding Author: I. P. Kavirayani, kindira@barc.gov.in
Radiation chemistry, a discipline involving study of chemical changes induced by ionizing
radiation, has been the subject of interest for both researchers and technologists. Extensive
research carried over the last few decades has translated into applications in the areas of
advanced materials, nuclear fuel cycle, radiotherapy, sterilization, waste treatment, water
purification, etc. Radiation chemistry of water as one of the important areas of research,
provided understanding of the primary processes of water radiolysis, the same has also
led to the progress of another related field, radiation biology. Hydroxyl (‚OH) radicals, a
powerful oxidant generated during water radiolysis, trigger sequences of events in the living
cells causing several changes including mutations in DNA and cell death. While this formed
the basis of radiotherapy for cancer treatment, the same became a matter of concern due to
unwanted normal tissue radiation damage. In order to minimize this unwanted radiation
damage to the normal tissue, radioprotectors are employed. Search for radioprotectors
began following the Second World War and after screening several thousand natural and
synthetic sulfur compounds, only one compound, amino thiol known as, “amifostine” has
been approved for clinical use.
Our recent experience in the research area of radiation chemistry of selenium compounds,
prompted us to find a new direction of developing radioprotectors from organoselenium
compounds. Selenium as a member of chalcogen group shares similarities with sulfur and is
a micronutrient and a constituent of redox active selenoenzymes like glutathione peroxidise.
A number of selenium compounds such as selenoethers, diselenides, monoselenides have
been synthesized and screened for radioprotection. Since ‚OH radical reaction is the pri-
mary process in radiation damage, the reactions of selenium compounds with ‚OH radical
were studied in real time scales. For these studies, pulse radiolysis, a time-resolved linear
electron accelerator based technique, used to follow chemical reactions in nanoseconds, was
employed. The results indicated that in these compounds, selenium is the active centre for
the attack of ‚OH radical and the reaction leads to formation of selenium centred radical
cation, which interacts with the nearby hetero atoms through non-bonding interactions.
Depending on the strength of interactions, the radical actions are converted to oxidized
products, which played a crucial role in deciding whether the selenium compound can
be explored as a radioprotector or not. Similar studies on several substituted selenocar-
boxylic acid derivatives suggested that a diselenide having propinoic acid substitution is
structurally best suited for developing as radioprotector. Accordingly, diselenodipropionic
acid examined in vivo systems was found to be a good organ specific radioprotector. Some
of these results will be presented in the lecture.
IAEA–CN–241–322 129
A07
A07-06 Talk: Session A07, Tuesday 18:10 Belyakov
The IAEA Research on Radiation Sterilization in Tissue Banking
O. Belyakov1
1International Atomic Energy Agency (IAEA), Vienna, Austria
Corresponding Author: O. Belyakov, o.belyakov@iaea.org
The IAEA programme on radiation and tissue banking is a major effort to establish and
improve tissue banks in Member States (MS). Started in 1971, it became supported by
IAEA’s Department of Technical cooperation in 1982, and there are a number of running
projects in this area coordinated by the Agency. Less known is that, apart from capacity
building by the TC, IAEA’s Department of Nuclear Sciences and Applications carried out
Adaptive Research and Development projects related to tissue sterilization. These two
directions of work reinforce each other and result in better Tissue Banking services in
MSs. IAEA Coordinated Research Project (CRP) E31006 on “Safety and optimization of
radiation sterilization in tissue banking: Studies on functional properties of irradiated tissue
grafts” was started in 2010 and completed in 2015. Sixteen organizations, represented by
Chief Scientific Investigators: Paulina Maria Estela Aguirre Herrera (CHI), Dr Emma Castro
Gamero (PER), Mark Forwood (AUS), Clara Linda Guerrero (COL), Marisa Herson (AUS),
Eulogia Kairiyama (ARG), Artur Marek Kaminski (POL), Astrid Ann Lobo Gajwala (IND),
Jan Koller (SLO), Menkher Manjas (INS), Monica Beatriz Mathor and Wilson Aparecido
Calvo (BRA), Peter Myint (UK), Isabel Maria Otero Abreu (CUB), María del Carmen Salidas
Farinella (URU), Suzina Sheikh Ab. Hamid (MAL), Sven Scheffler (GFR) contributed to this
project.
The use of tissue allografts in surgical procedures has increased tremendously over the last
two decades. Radiation has been used to sterilize tissue allografts on a large scale. Contro-
versies exist regarding the optimal dosage required since radiation may also compromise
tissue allograft integrity and/or its biological function. Tissue banks use radiation doses just
based on empirical and/or historical data, or use a fixed dose of 15 or 25 kGy for all tissue
allografts. Moreover, radiation conditions differ very strongly from institute to institute
which may strongly influence the efficacy of the radiation treatment. In order to improve
the knowledge on radiosterilization of tissue allografts “new” and additional studies were
designed and conducted under controlled and validated conditions. This “new knowledge”
will lead to an optimization of the radiation sterilization process/procedures.
Five main categories of research topics were studied: Bone, Demineralized bone, Cartilage
allograft, Skin and Amnion. Bone: Adoption of sterilization doses below 15 kGy improves
tissue quality and surgical outcomes. Demineralized bone (DMB): Sufficient osteo-induction
was observed after experiments using DBM treated at 15 kGy radiation dose. Cartilage:
Present studies demonstrated that optical coherence tomography (OCT) is a suitable non-
destructive technique to evaluate costal cartilage change after sterilization by ionizing
radiation. Skin: Most sensitive tissue to structural changes induced by radiation proved to
be animal skin, least sensitive human skin. Irradiation dose up to 25 kGy had minor impact
on the ultrastructure of the irradiated skin and its functionality (evaporation index).
It can be concluded that since 2010 significant progress has been made by the participating
tissue banks/institutes leading to the production of safer allografts both with respect to its
functionality and sterility.
130 IAEA–CN–241–213
A07
ICARST–2017
A08:Radiation Sources and Facilities:
Panel Discussions
131
A08
A08-01 Talk: Session A08, Wednesday 09:00 Dethier
Review of the Two New Rhodotron Accelerators: The Compact
10MeV TT50 and the High Energy 40MeV Rhodotron
P. Dethier1
1IBA, 1348 Ottignies-Louvain-la-Neuve, Belgium
Corresponding Author: P. Dethier, philippe.dethier@iba-group.com
Emerging applications drive development of new innovative accelerators. IBA is currently
developing two new accelerators. The first new accelerator is a compact electron beam
accelerator called the TT50 allowing to produce beam up to 10 MeV. This accelerator is
perfectly suited for industries sensitive to cost such as cargo screening, medical device
sterilization or applications requiring mobile systems.
The second new product under development is a high energy Rhodotron able to reach
40 MeV and 125 kW of beam power. These specifications makes 99Mo production using
particle accelerators very competitive. Development status, innovations and target perfor-
mances will be reviewed.
132 IAEA–CN–241–024
A08
Wiens Talk: Session A08, Wednesday 09:20 A08-02
A Billion Curies and Counting: Ensuring 60Co Supply and
Disposal for Decades to Come
R. Wiens1
1Nordion Inc., Canada
Corresponding Author: R. Wiens, richard.wiens@nordion.com
Nordion has been a leader in the production of 60Co, used for prevention and treatment
of disease, since the inception of the technology in the 1950s. This product has become a
critical component of healthcare, impacting the daily lives of millions of people around the
world.
Since the production of the first C-188 60Co source in 1964, Nordion has shipped more than
one billion curies of Cobalt for use by the γ-processing industry. During this 50 year period,
there have been significant changes in technology, regulation and the global supply chain.
Our approach to managing the full lifecycle of the C-188, from sourcing to production to
transportation to disposal, has allowed us to adapt to these changes and continue to provide
a reliable supply of Cobalt to a global customer base
Today, we face a changing reactor landscape and new industry dynamics that offer both
challenges and opportunities. Our Extend, Expand, Develop strategy is aimed at exploring
a wide array of possibilities for strengthening the supply chain for the coming decades. We
now have more than 20 active projects under way, from the development of new technology
platforms to enhancement of existing partnerships, as well as the creation of new ones. We
also continue to make use of established paths for disposal of spent sources, while pursuing
other solutions in order to provide the best options for the industry.
This presentation will describe the evolving industry landscape as we see it, and provide an
update on Nordion’s efforts and successes around securing supply of 60Co and managing
the complete lifecycle for the long term.
IAEA–CN–241–432 133
A08
A08-03 Talk: Session A08, Wednesday 09:40 Han
How to Apply Radiation Technology for Pollution Control
B. Han1, J. Kim1, and Y. Kim1
1EB TECH Co. Ltd., Republic of Korea
Corresponding Author: B. Han, bshan@eb-tech.com
Since the 1980’s, radiation technology has been introduced to pollution control, and over
the past few decades this technology has been developed aiming at ensuring the safety
of gaseous and liquid effluents discharged to the environment. It has been demonstrated
that flue gas treatment (SOx and NOx removal), wastewater purification and sludge hygi-
enization by radiation can be effectively deployed to mitigate environmental degradation.
They even showed promising results through the operation of several pilot scale plants
and industrial scale implementation, however, the technology was boggled and it needs
to achieve a breakthrough. There are several drags to implement larger scale applications.
Unlike other industrial applications, the environmental plant should operate all the year
round without stopping. Once it stops, the waste (stack gas or wastewater) will discharge
without any treatment, and the stand-by system costs too much. Thus, technical upgrades to
manage the plants in such cases are required. Radiation technology, like other technologies,
also has strong competition in market with conventional pollution treatment technologies.
And hence, it is necessary to decrease the capital cost with the operating cost to have competi-
tiveness in waste treatment cost. Nowadays, radiation processing equipment is getting more
powerful and reliable, and ready to apply for pollution control, but requires a systematic
operation for preventing the entire plant shutdown. To avoid tough competition, it is better
to find niche applications where radiation technology can do better, such as removal of
EDCs and pharmaceutical residues in domestic wastes, VOCs removals from industries
or sludge hygienization. Computational methods, mobile EB and other effective ways to
confirm laboratory results will help for easy scaling to industrial implementation.
134 IAEA–CN–241–145
A08
Bryazgin Talk: Session A08, Wednesday 10:00 A08-04
ILU Industrial Electron Accelerators
A. Bryazgin1, V. Bezuglov1, A. Vlasov1, L. Voronin1, M. Korobeynikov1, A. Lukin1,
S. Maximov1, V. Nekhaev1, F. Nikonov1, A. Panfilov1, V. Radchenko1, A. Sidorov1,
V. Tkachenko1, B. Faktorovich1, and E. Shtarklev1
1Budker Institute of Nuclear Physics (BINP), Novosibirsk, Russian Federation
Corresponding Author: A. Bryazgin, bryazgin@gmail.com
ILU electron accelerators designed and produced in Budker Institute of Nuclear Physics
are working in industry and in research organizations. ILU-8 and ILU-10 machines have
single-cell cavities, their maximum energies are 1 MeV and 5 MeV, maximum beam powers
are 20 kW and 50 kW respectively. The recently developed ILU-12 and ILU14 machines
have multicavity accelerating structures, their energy ranges are 5–7.5 MeV and 7.5–10 MeV,
maximum beam power of ILU-14 is 100 kW. Radio frequency (RF) generators of the ILU
machines are based on pulse vacuum triodes. Compact accelerator ILU-8 with energy
up to 1 MeV is using mainly for wire irradiation, it has local radiation shield. All other
ILU accelerators can be supplied with X-ray converters and can work in X-ray generation
mode. Powerful ILU accelerator are used for wire, cable and pipe modification as well as
for medical device sterilization and food irradiation.
IAEA–CN–241–102 135
A08
A08-05 Talk: Session A08, Wednesday 10:20 Peng
EB Technology vis-a-vis γ-Radiation for Irradiation Sterilization:
Emerging Scenario
W. Peng1
1Vanform Corporation, Jinan, Shandong, China
Corresponding Author: W. Peng, pewwy@163.com
Irradiation sterilization as a green and safe sterilization method is widely used in the
treatment of food, medical products, herbals and agricultural products worldwide. The
main technologies for irradiation sterilization are γ-radiation and electron beam technology
which includes EB and X-ray. Technology based on 60Co was developed more than half a
century ago, but following the continuous concerns on the radiation safety, nuclear security,
radioactive waste and the supply of 60Co sources, the development of γ radiation for
irradiation sterilization faces more and more challenges. Electron beam based technology
was developedmuch later relative to γ technology. As the need of alternativemethodswhich
do not use radioactive material for irradiation sterilization, EB technology has developed
very rapidly in the last decade.
The presentation provides a general analysis of the advantages and drawbacks on different
aspects such as regulation requirement, safety and security, products scope, economic
competitive for both γ and EB technologies and will provide some suggestion and outlook
for this emerging scenario of irradiation sterilization.
136 IAEA–CN–241–037
A08
Kohli Talk: Session A08, Wednesday 10:40 A08-06
γ-Irradiator Technology: Challenges and Future Prospects
A. K. Kohli1
1Department of Atomic Energy, Mumbai 400 001, India
Corresponding Author: A. K. Kohli, cebrit@gmail.com
γ-irradiator technology has served the bulk irradiation industry very well. Sterilization
of medical disposables has been the most popular application followed by irradiation of
food and other products. However, it has faced number of challenges in its journey so far.
The initial irradiators utilized 137Cs sealed sources in highly soluble chloride form. Wet
storage irradiators had risk of contamination due to 137Cs sources. There were incidents of
irradiator facility and surrounding soil contamination due to source leakage. Availability
of 60Co in metallic form came handy to surmount this challenge. Over-exposure of plant
personnel while carrying out maintenance has been reported. With the improvements in
safety systems, this challenge was adequately tackled. Later, shortages of 60Co in addition
to high prices coinciding with availability of the challenger linear accelerator technology
became the biggest challenge. Higher capital cost in addition to higher running cost of the
LINACs was though a deterrent. Also, non-availability of reliable power supply in different
parts of the world was an additional factor in accelerators not replacing γ irradiators at
faster pace.
Themost recent challenge to γ irradiator technology has come due to the heightened security
risk the world is facing now. There are fears being raised regarding security of the high
intensity radioactive sources in such irradiators. The security challenge is due to fear of
the sources falling into the wrong hands. This possibly could happen when sources are
in installed position or more so during their transportation. Such fears have forced the
authorities to strengthen regulations. Shipping companies have become reluctant to carry
radioactive materials, particularly when trans-shipment is involved. There are number of
instances of denial of shipments making the situation worse. The maximum activity which
can now be carried in a Type B(U) container is also limited to only 30 kCi of 60Co whereas
the requirements in industrial irradiators is much higher which makes the transportation by
air exorbitantly expensive. The other requirement of regulatory body to obtain guarantee of
return of sources to the original supplier is an additional impediment. To prevent source
theft when it is in installed position, hardening of facilities or devices needs to be carried out
so that response time for the security agency in case of theft attempt is shorter than what is
needed by the adversary to remove the sources from the device and shift those to amakeshift
container. Lastly, challenge due to possible dismemberment of installed sources which can
result in large areas becoming inaccessible due to contamination is forcing operators to
think hard before making a choice.
Accelerator technology being “On-Off”, does not have such drawbacks. Because of this,
LINACs have gained much higher importance in recent times. However, LINAC’s lower
efficiency of conversion of energy to electromagnetic radiation and its dependence on
availability of economic and reliable power supply will eventually decide the time at which
it replaces the γ irradiator technology fully in any particular part of the world.
IAEA–CN–241–010 137
A08
ICARST–2017
A09: Preservation of Cultural Heritage
138
A09
Havermans Talk: Session A09, Wednesday 11:15 A09-01
Disinfection and Consolidation of Archived Materials and
Cultural Heritage Artefacts by Radiation Processing Techniques
J. Havermans1, C. Ponta1, T. Quoc-Khoi2, P. Vasquez3, and J. L. Boutaine4
1TNO Environmental Modelling, Sensing and Analysis, The Hague, Netherlands
2ARC-Nucléart Conservation Center, CEA, Grenoble, France
3Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), São Paulo, Brazil
4Centre de Recherche et de Restauration des Musées de France (C2RMF), Paris, France
Corresponding Author: J. Havermans, john.havermans@tno.nl
Degradation of organic and especially cellulose based heritage is caused by both endogenous
and exogenous factors. One of the most common exogenous factor is moisture, and the
variation of the equilibrium moisture content of the material can initiate the development
of mold in the substrate. Mold not only affects cellulose materials, but is also impacts
occupational health and thus should be rendered inactive as soon as possible. Doing
nothing is not an option because active mold (even dormant) may deteriorate cellulose
based heritage easily, while its wake-up call, i.e., an atmospheric moisture increase, can
occur easily.
Much work has been performed on the application of γ-radiation and therefore it is well
accepted in, e.g., the food industry and for medical device sterilization. However for cultural
heritage application, discussions are still on-going as ionizing radiation may be capable
of deteriorating organic materials. Compared to conventional disinfection with chemicals,
γ-radiation can be seen as a clean disinfection method as no harmful volatiles are emitted
after the treatment with full effectiveness on deteriorating the mold species.
In the past decade, many heritage science research programmes world-wide were dedicated
to the application of ionizing radiation for disinfection and conservation. The research
varied from optimization of the treatment to understanding of deterioration mechanisms,
and in 2012 for the first time, an IAEA supported event was held in São Paulo, Brazil. The
IAEA now supports a new research network dedicated to this topic aiming to solve final
research gaps and produce well accepted recommendations.
This paper reviews not only the state-of-the-art of international developments on the appli-
cation of ionizing radiation for cultural heritage for both disinfection and conservation, but
includes a summary of show-cases. For example, the disinfection of the Library collection
of the Peace Palace, the Hague (Netherlands) and conservation of a XVIIIth century par-
quet, Grenoble (France). Finally a novel book dedicated to the topic of this presentation,
supported by the IAEA, shall be introduced.
IAEA–CN–241–033 139
A09
A09-02 Talk: Session A09, Wednesday 11:35 Katušin-Ražem
Irradiation Method in the Protection of Cultural Heritage
Objects Endangered by Massive Biodegradation
B. Katušin-Ražem1, B. Mihaljević1, and M. Braun2
1Ruđer Bošković Institute, Zagreb, Croatia
2Croatian Conservation Institute, 10000 Zagreb, Croatia
Corresponding Author: B. Katušin-Ražem, brazem@irb.hr
Cultural heritage artefacts of organic origins are susceptible to deterioration by the action of
insects, moulds, fungi and bacteria. The infestation of museum store rooms, collections and
sacral places is a serious permanent worldwide problem to the safekeeping of such objects.
Protecting cultural heritage objects against biodeterioration becomes especially urgent when
provoked by sudden changes of their stable and optimum storage conditions, caused either
by natural catastrophes (floods, earthquakes, tempests, etc.) or by human activities (wars,
riots, street unrest, etc.). The emergency recovery of many objects in the course of a rescue
operations can bring infested and non-infested objects into contact, engendering an abrupt
development of pests and endangerment of whole collections.
The commonly used methods for suppressing massive biocontamination (capable of fast
processing of large numbers of objects), are treatment with poisonous gasses and treatment
with ionizing radiation. While the use of ethylene oxide gas is now severely restricted,
irradiation has proven an effective physical, noncontact method of preservation, applicable
to massive treatment of cultural heritage objects.
In its „ 50 years of application to cultural heritage preservation, the irradiation method
has most often been used for disinsection, i.e., eradication of insect pests from objects. In
the course of safekeeping, massive treatments of entire museum collections during regular
and/or urgent maintenance and clean-up procedures provide examples of especially appro-
priate applications of irradiation method. Likewise, in cases of simultaneous endangerment
of many objects by mold, literally for entire collections caught up in catastrophes, the irradi-
ation method has proven to be the method of choice. Professional literature presents some
especially successful cases of massive decontamination by irradiation and it will be briefly
presented in the lecture.
Croatian experience in the field gained at the irradiation facility of the Radiation Chemistry
and Dosimetry Laboratory of the Ruđer Bošković Institute in Zagreb during the past 25
years will be illustrated by two groups of examples of successful application of irradiation
to the protection of large numbers of cultural heritage objects endangered by massive
biocontamination: a) Massive radiation desinsection in the process of maintenance of
museum collection and interventive treatment of an entire polychromic altar; b) Radiation
treatment in the massive process of rescuing and protecting art objects endangered during
the war in Croatia (1991–1995).
In co-operation with the Croatian Conservation Institute, one third of evacuated objects,
mostly polychromic wooden sculptures, parts of altars and other wooden pieces, comprising
almost 1500 complete altars, were irradiated for disinsection, or disinfection by the RBI
facility. Besides halting degradation, irradiation was used as the first step of conservation to
enable safe object storage without the risk of cross-contamination before final conservation
and restoration.
140 IAEA–CN–241–330
A09
Moise Talk: Session A09, Wednesday 11:55 A09-03
Radiation Processing for Cultural Heritage Preservation:
Romanian Experience
I. V. Moise1
1Horia Hulubei National Institute for R&D in Physics and Nuclear Engineering, Romania
Corresponding Author: I. V. Moise, vmoise@nipne.ro
Radiation sterilization was taken into consideration as a mass decontamination techniques
for the biodegradable cultural heritage (CH) as soon it was spread in the medical field.
Earlier experiments showed the advantages and disadvantages, namely “side-effects” on
the CH materials. More than 50 years later, the suitability of ionizing radiation treatment
for CH items is still under debate. The main reason is that science and industry were not
yet able to provide another mass decontamination technique with higher efficiency and
effectiveness.
For wood items there is a general agreement that the irradiation dose needed for insect
eradication will not produce any damage, even in case of painted wood. For cellulose in
paper there is a reduction of the degree of polymerization (DP) at higher doses required for
stopping the fungal attack but this should be taken into consideration against the purpose of
the treatment. Emergency or salvage treatments are required for mitigation of consequences
of accidents or bad storage conditions. In some cases (archives) the value of the written
information is higher than the historical value of paper artefact. For other materials (textiles,
leather, parchment) there are less published investigations on the effects or ionizing radiation.
As a general rule, irradiation is not needed when there are only few CH items affected by
biological contamination. The conservators and restaurateurs can handle the problem by
classical means. The need for irradiation appears when there are large collections (hundreds,
thousands or more items) heavily affected by biological attack.
Following new literature reports there is a slow increase in the quantities and kinds of
irradiated CH items in different countries of the world. In Romania, IRASM γ-irradiator of
IFIN-HH is receiving an increasing number of requests for CH irradiation, mainly because
an intensive research programme on this topic and a close contact with the CH owners or
administrators. After more than 10 years of CH irradiation, IRASM facility can advise the
CH owners about choosing the irradiation dose and how to evaluate the irradiation side
effects (if any). Beside the review of the scientific results obtained in Romania and abroad,
this paper will present some examples from Romanian experience.
IAEA–CN–241–438 141
A09
A09-04 Talk: Session A09, Wednesday 12:15 Tran
Development of New Radiation-Curing Monomers-Resins
Systems for the Consolidation of Wooden Cultural Heritage
Artefacts
Q.-K. Tran1
1ARC-Nucléart CEA, Grenoble, France
Corresponding Author: Q.-K. Tran, quoc-khoi.tran@cea.fr
The styrene unsaturated polyester resin is implemented so far by ARC-Nucléart Conser-
vation Centre for the consolidation of degraded wooden artefacts from cultural heritage,
following a process so-called “Nucléart” by liquid state resin impregnation under vac-
uum/pressure, and in situ polymerization of the resin under γ-irradiation. However, this
method is irreversible due to the cross-linked solid state resin which is insoluble in any
solvent, and moreover, the consolidation of wood by such 100% reactive resin fills almost
completely the wooden pore structure, creating in fact a wood-plastic composite which has a
density much higher than untreated wood. These features are the drawbacks of the method
because in conservation-restoration of art objects, the two well-known criteria among others
are the reversibility of the products and the minimal intervention in order to avoid the
denaturation of the original and unique object.
Having proven during many decades its effectiveness for saving from destruction numerous
highly degraded artefacts, another drawback of the actual process is the more severe regu-
lation in terms of safety, toxicity when using the styrene monomer, without considering its
high vapour pressure and its residue in treated artefacts even after long periods of storage
or display. For these different reasons, the aims of our research are the improvement of
our radiation method in two directions: the application of already available styrene-free
resins, and the development of hydroxyl-acrylic monomers which polymers are in principle
reversible, respecting one of the most important criteria in conservation. In this paper, we
will describe first the irradiation conditions to overcome the inhibition effect of oxygen on the
complete curing of the resin or monomers, the formulations of monomers in order to obtain
polymers with the most appropriate Tg (around 40˝ to 60˝C), and their polymerization
in selected solvents in order to modulate their content in the wood. Structural character-
izations are carried out by using FTIR and solid state NMR spectroscopies. The second
part of our work will present the impregnation of two species of wood, beech and fir, by
styrene-free selected resin and by monomers. They are characterized by various techniques
such as colourimetry, dimensional changes, radiography, computerized tomography, and
mechanical resistance. Last but not least, the interaction (or not) of the resins or monomers
with various polychromies (pigments, colourants) has to be checked, and it is important
to assess the feasibility of their implementation in consolidation of samples of sacrificed
artefacts presenting gilded or polychrome surface layers.
142 IAEA–CN–241–303
A09
Baccaro Talk: Session A09, Wednesday 12:35 A09-05
Application of Ionizing Radiation for Cultural Heritage
S. Baccaro1, A. Cemmi1
1Agenzia nazionale per le nuove tecnologie, l’energia e lo sviluppo economico sostenibile (ENEA), Rome, Italy
Corresponding Author: S. Baccaro, stefania.baccaro@enea.it
Ionizing radiation has specific and indisputable advantages over classical procedures for
conservation and preservation in cultural heritage, such as no risk for the operators, no toxic
residues and hence no risks for curators, visitors or the environment. This technology can
replace the traditionally used toxic or carcinogenic gases such methyl bromide or ethylene
oxide, eliminating the associated health problems and environmental pollution. Large
amount of biodeteriorated objects can be treated in a short time with excellent reliabil-
ity, using controlled and codified procedures. The evaluation of the often nonreversible
physical-chemical modification induced by ionizing radiation on treated materials, namely
side-effects, represent an important goal to guarantee the safeguard of the artefacts and the
reliable diffusion of this technology. Irradiation procedures and characterization method-
ologies will be assessed for the conservation and preservation of archive materials and for
the consolidation and protection of porous artefacts. Defined irradiation conditions (in
terms of irradiation dose and dose rate, environmental atmosphere, pretreatment of the cul-
tural heritage object) and the proposal of shared guidelines are extremely desirable. ENEA
activities regarding the application of ionizing radiation in cultural heritage performed at
Calliope plant are focussed on conservation and preservation (biodeteriogen eradication
in archived materials) and on consolidation and protection (degraded wooden and stone
porous artefacts consolidation). The biocide effect of γ radiation has been confirmed on
selected papery materials at dose effective for the treatment and the harmful effects on the
irradiated materials have been demonstrated.
With the aim to be effective for disinfestation, microbiological studies about the dose rate
and atmosphere (air and inert gas) effects on γ-irradiated archived materials have been
performed. Irradiation side-effects on paper have been also investigated by chemical and
spectroscopic techniques (DP, FTIR, ESR). Different atmospheric and biological agents
induce severe and somewhat irreversible degradation phenomena on wooden or stone
artefacts (i.e., porous materials). Consolidation and surface protection of these degraded
objects is usually obtained by the application of natural or synthetic consolidating agents
but the penetration inside the porous material it rather difficult, limiting the effectiveness
of the treatment. Impregnation of cultural artefact with a diluted solution of consolidant
precursors (i.e., low-sizes monomers or oligomers) followed by radiation induced in situ
polymerization represents a very promising solution to achieve actual bulk strengthening.
Formulation of different polymeric composition for the consolidating agents to improve
their strengthening efficacy and safeguard towards the cultural object has been investigated,
modifying their features by γ irradiation and aiming to increase their functional, chemical
and time stability. Particular attention has been paid on the solvent compatibility, aiming at
employing environmentally friendly and human nontoxic substances. Characterization by
means of different techniques (opticalmeasurements, FTIR, ESR,NMR,mechanical tests) has
been carried out to evaluate side-effects and the postirradiation behaviour. Standardization
of irradiation procedures and methodologies by a correct choice of irradiation parameters
and their reliability and reproducibility has been verified and supported by dosimetric
measurements.
IAEA–CN–241–304 Presenter: A. Cemmi 143
A09
A09-06 Talk: Session A09, Wednesday 12:55 Cortella
Uses and Prospects in γ-Biocide Treatments for Cultural Heritage
L. Cortella1, C. Albino1, C. Salvan1, and Q.-K. Tran1
1ARC-Nucléart CEA, Grenoble, France
Corresponding Author: L. Cortella, laurent.cortella@cea.fr
Biocide treatment by γ-irradiation for wooden and archival items has been proposed more
than 50 years ago, but, despite some resounding success and a demonstrated real efficiency,
it is still of limited uses for heritage conservation. Indeed, if such denoted “nuclear” pro-
cess can scare the less scientific public, more rational reluctance due to fear of negative
effects induced by ionization in irradiated material have been expressed. Despite such,
secondary effects are usually insignificant or very low, γ irradiation has been (and is still)
often understood by many curators as resulting in a strong and irreversible degradation,
comparable to well-known ultraviolet exposure ageing. Of course, as with any process in
which we ask to be active— in this case to kill biodegrading species— it is impossible to
ask for absolute harmlessness. Any biocide process, as innovative or not as it is, can be
problematic. Anoxia is known to induce colour changes of some dyes. Ethylene oxide, not
only being very dangerous, is very reactive. Temperature treatments can cause mechanical
tensions and so on. In choosing between different ways to manage pest infestation, curators
have to evaluate a balance between benefits and drawbacks, selecting the best compromise
regarding the conservation issue (including the benefits and drawbacks of “doing nothing”).
In this context, advantages of the γ irradiation are various. Beyond its proven effectiveness
on any kind of living organism, whatever the life stage, this contactless technology meets
very well the concept of minimum intervention, being able to insure the required successful
conservation with very low impact, only “changing as much as necessary but as little as
possible”. The ability to treat by mass, even through packaging, and the absence of other
associated heat effect or residue in processed materials are two other desired qualities. But
it is definitively its reliability, besides its efficiency, which distinguishes γ irradiation, thanks
to γ penetrating power and the facility to ensure that biocidal conditions are achieved
everywhere in the volume.
In the other hand, possible secondary effects need to be evaluated carefully. Material
behaviour under irradiation is studied in the field of heritage, as well as it is widely investi-
gated in many areas (nuclear, space, medical, etc.). Effects depend largely on the type of
material and on the absorbed dose. Very few materials are known to be incompatible with
γ-irradiation biocide treatment. The possible interaction with informative properties of
patrimonial goods (DNA information, dating parameters) is another relevant issue.
ARC-Nucléart, Grenoble, France, makes use of γ irradiation for more than 45 years for
cultural heritage. While insects are most often targeted, mass treatment of fungal species
contaminated collections are more and more demanded. It seems that during the last 10 or
15 years, it is also increasingly used around the world.
We will give an overview of the latest developments of this technique, both in actual use in
France, and in the studies that are ongoing to quantify so-called secondary effects.
144 IAEA–CN–241–398
A09
ICARST–2017
A10:Development in Electron Accelerators
Technology
145
A10
A10-01 Talk: Session A10, Wednesday 16:30 Zhang
Addressing Challenges Posed by Electron Beam Irradiation
through Innovation
Y. Zhang1
1Wuxi El Pont Radiation Co., Ltd., Jiangsu, China
Corresponding Author: Y. Zhang, yuwei.zhang@elpont.net
Over the past decade, the use of electron accelerators for sterilization and disinfection
has made considerable progress and the offer has greatly diversified. The challenges that
γ-technology is facing has also raised considerable interest in EB and X-ray technology as a
possible alternatives to the use of radioisotopes.
However, commercial operation of electron accelerators faces several challenges. The pene-
tration depth of electron beams, even at 10 MeV, does not permit processing all commercial
packages that are encountered. Companies operating a single EB machine are often con-
fronted with downtime that results in production delays due to the time necessary for
repairs.
The presentation will introduce an innovative solution that overcomes these challenges and
was designed and proven through a long and broad experience of using and manufacturing
electron accelerators. This solution is based on an optimal mix of electron accelerators types
(Linac and HFHV), different energies (10 MeV and 5 MeV) and different types of ionizing
radiation (EB and X-ray). A recent example of successful use of this combination will be
shown.
146 IAEA–CN–241–060
A10
Cooper Talk: Session A10, Wednesday 16:50 A10-02
Illinois Accelerator Research Center
C. Cooper1
1Fermi National Accelerator Lab (Fermilab), Batavia, IL 60510-5011, USA
Corresponding Author: C. Cooper, ccooper@fnal.gov
The Illinois Accelerator Research Center (IARC) hosts a new accelerator development pro-
gramme at Fermi National Accelerator Laboratory. IARC provides access to Fermi’s state-of-
the-art facilities and technologies for research, development and industrialization of particle
accelerator technology. In addition to facilitating access to available existing Fermi infrastruc-
ture, the IARC Campus has a dedicated 36 000 sqft heavy assembly building (HAB) with all
the infrastructure needed to develop, commission and operate new accelerators. Accelerator
infrastructure available for use in collaborative efforts will be detailed. Connected to the
HAB is a 47 000 sqft Office, Technology and Engineering (OTE) building, paid for by the
state, that has office, meeting, and light technical space. The OTE building contains the
Accelerator Physics Center, and with nearby Accelerator and Technical divisions, provides
IARC collaborators with unique access to world class expertise in a wide array of accelerator
technologies. IARC scientists and engineers from Fermilab and academia work side by
side with industrial partners to develop breakthroughs in accelerator science and translate
them into applications for the nation’s health, wealth and security. Some of the current
collaborative efforts will be detailed.
IAEA–CN–241–264 147
A10
A10-03 Talk: Session A10, Wednesday 17:05 Kroc
A Compact Superconducting RF Accelerator for Electron Beam
and X-Ray Irradiation
T. Kroc1
1Illinois Accelerator Research Center (IARC), Warrenville, IL 60555, USA
Corresponding Author: T. Kroc, kroc@fnal.gov
As commercial and industrial applications of electron beam and X-ray irradiation have
developed, new applications have emerged that require very high beam power to create the
required radiation field. These new applications require dependable, efficient, high energy,
high power electron accelerators.
Recent developments in superconducting radio-frequency (SRF) technology can now en-
able accelerators with lower costs and improved performance. Cryogenic heat loads are
dramatically reduced through use of newmaterials and improved component designs. New
cooling methods allow the replacement of complex systems requiring cryogenic fluids with
simple robust systems with no fluids. New RF sources can greatly reduce the cost of RF
power. Each of these developments has been individually proven and an effort is underway
at the IARC at Fermilab to integrate them into the first prototype of an entirely new class of
industrial SRF-based accelerators. These accelerators will enable robust, turn-key operation
with very high electrical efficiency. The accelerator prototype under designwill be capable of
10 MeV beam, CW operation, and 250 kW of electron beam power. These modular systems
are small enough to be palletized and transported to the point of use. Their high electrical
efficiency mean that portable power generation systems can be enable their use in mobile
applications.
The goal is a compact, cost effective, high power accelerator suitable for many of the ap-
plications covered by this conference. Fermilab is actively working to build the prototype
and identify partners for commercialization. The end product will be a commercially avail-
able, robust, turn-key system for applications requiring reliable electron beam or X-ray
irradiation.
148 IAEA–CN–241–122
A10
Roegner Talk: Session A10, Wednesday 17:20 A10-04
Low-Energy Electron Irradiation for Novel Applications in
Medical Production and Pharma
F.-H. Roegner1, J. Portillo Casado1, S. Ulbert2, A. Weidauer1, and M. Thoma3
1Electron Beam and Plasma Technology (FEP), Fraunhofer Institute for Organic Electronics,
01109 Dresden, Germany
2Fraunhofer-Institute for Cell Therapy and Immunology IZI, 04103 Leipzig, Germany
3Fraunhofer Institute for Manufacturing Engineering and Automation IPA, 70569 Stuttgart, Germany
Corresponding Author: F.-H. Roegner, frank-holm.roegner@fep.fraunhofer.de
Currently most γ or high energy EB ionizing irradiation processes for medical and phar-
maceutical production are provided by external services. Only a few applications rely on
low energy electron irradiation: e.g., syringe tub sterilization at high throughput filling
lines. But more complex and expensive logistics as well as demands for flexibility in small
customized production batches calls for an irradiation processes integrated into the produc-
tion chain. The simple implementation of irradiation technologies into typical production
environments. is hindered by the limited penetration depth of low energy electrons and the
expense of multisource arrangements needed for 3D-objects. Therefore, Fraunhofer FEP
and partners has developed a new low energy electron irradiation application available
for production integrated solutions. To avoid multisource arrangements for homogeneous
irradiation of 3D-objects, a toroidal shaped electron beam source was developed. By using
high-voltage glow discharge for electron generation, a compact and robust electron source
for energies up to 150 kVwas born. Original targeted for treating bulk goods, a single source
is perfectly adapted for surface modification or sterilization of 3D products like implants, or
continuous feed material like tube packaged parts. First experimental results of operation,
the electron generation principle and the first application (seed treatment) will be presented.
Liquids irradiation traditionally requires high energy irradiation because of the penetration
depth requirements. Especially in the case of vaccine production, virus inactivation by
irradiation is very interesting because of the high efficiency in antigen conservation. But
high energy irradiation at external facilities is not practicable because of the strong safety
requirements. Within an ongoing Fraunhofer funded project, an interdisciplinary team
developed a low energy irradiation method for virus containing suspensions to produce
inactivated but still very efficient vaccines. Actually results about irradiation technology
and vaccine testing will be presented. The new inactivation technology will make vaccine
production faster and cheaper with higher efficacy at the same time.
Together with some actually additional development directions like:
• Miniaturized electron beam sterilization compartment for on-site sterilization of
packaged products;
• Electron beam modification of cell-therapeutic substrates;
we can show an enormous potential for low electron irradiation processes in medical and
pharmaceutical production.
More flexibility in small batch production and a close production chain inside the facility
increase the safety level and the production efficiency at the same time. Low energy electron
irradiation will play an important role in this paradigm change over the next years to fulfil
the requirements of more than just the healthcare industry.
IAEA–CN–241–054 149
A10
A10-06 Talk: Session A10, Wednesday 17:50 Kuksanov
DC ELV Accelerators: Development and Application
N. Kuksanov1, R. Salimov1, S. Fadeev1, and P. Nemytov1
1Budker Institute of Nuclear Physics (BINP), Novosibirsk, Russian Federation
Corresponding Author: N. Kuksanov, kuksanov47@mail.ru
ELV accelerators are widely used for electron beam processing. The use of these machines
enabled developing the manufacture of a wide range wires, cables and heat-shrink goods,
films, bands and so one. All of them are of high security and reliability during operation as
under standard and extreme operating conditions. ELV are DC electron accelerators with
high electron beam power. The conversation efficiency of electricity to electron beam power
is also high. The Budker Institute of Nuclear Physics (Novosibirsk, Russia) had started
activities with ELV accelerators in the 1970’s, at the request of former USSR cable industry.
Since then, over 140 accelerators were delivered inside Russia and abroad.
The ELV accelerator can be equippedwith awide set of supplementary devices extending the
application range. There are systems of ring and double side irradiation, 4-side irradiation
system, extraction device for focussed electron beam, transportation systems for cable, film
and grain. There are special devices to improve of dose uniformity during film and band
irradiation. ELV accelerators can be easily integrated in the technological processing given
its computerized control system. We study the requirements of accelerator market and
follow the requests of electron beam technologies users. The normal operating lifetime of
accelerators is some tens of year. Very often the modification of an accelerator for users is
more attractive in comparison to the capital cost of installing a new machine. So very often
old accelerators have upgrades and continue in operation.
The development of ELV accelerators is concerning with: stability in operation, new energy
region (the minimum energy became 200 keV instead of 400 keV. Accelerators with energy
less 1.0 MeV can be assembled inside the steel local shielding. There was developed the
system after warranty service of delivered accelerators. We are manufacturing ELV accel-
erator both inside BINP and in collaboration with South Korean and Chinese firms. An
accelerator with 400 kW electron beam power was developed and manufactured together
with EB-TECH Co.
150 IAEA–CN–241–380
A10
Weidauer Talk: Session A10, Wednesday 18:05 A10-07
Electron Treatment of Seed
A. Weidauer1, F.-H. Roegner1
1Electron Beam and Plasma Technology (FEP), Fraunhofer Institute for Organic Electronics, 01109 Dresden,
Germany
Corresponding Author: A. Weidauer, andre.weidauer@fep.fraunhofer.de
Providing the world’s growing population with nutritious food is an enormous challenge,
that solution starts very early in food production. Beside the known chemical seed dressing
there is another way for killing pathogens. Electrons are a versatile tool for numerous
applications in all fields of industry. Beside the known and established processes inmedicine
and pharma, the electron treatment of seed becomes more and more important. This
environmental friendly, purely physical disinfection of seed, is based on the biocidal effect
of accelerated electrons.
The penetration depth of the electrons into every single seed grain can be adjusted via the
kinetic energy of the impinging electrons. Thus, the sterilizing effect can be restricted to the
surface, pericarp and tegument, without affecting the seed embryo inside the seed grain.
The Fraunhofer FEP developed a technology that allows treating seed in air in a continuous
process. Thus, two large plants with throughputs up to 30 tons of cereals per hour were
constructed and successfully established in Germany. Large field tests, among others by
federal institutes, shows the success and comparability in field yield to conventional seed
dressings, without the disadvantages of chemical treatment, like the environmental effects,
dressing dust and the high costs of the chemicals. Beside the treatment of cereal seed, FEP
and its partners proofed the feasibility of killing bacteria such as E. coli on sprouting seed.
Due to the current demands, and following on the heels of the EHEC crises in 2011, there is
a growing demand for safe pathogen killing measures.
Infected seedswere treatedwith electrons and their resulting germination force, germination
rate and pathogen loads are investigated. More than 90% of the fenugreek and clover
samples and more than 80% of the mung bean samples are sterile, proved with fluid
turbidity tests, after electron treatment. Not to influence the embryo, can be proved by
testing germination rate and germination force. Both are kept unchanged. Tests show that
the treatment of sprouting seed (Mung bean, clover and fenugreek) to reduce bacteria load
is possible, without influencing the embryo.
IAEA–CN–241–106 151
A10
ICARST–2017
A11: Safety and Security Perspectives of Radiation
Facilities
152
A11
Frenzel Talk: Session A11, Thursday 09:00 A11-01
Upgrading Safety and Security of γ-Irradiation Facilities:
Possibilities and Limitations
M. Frenzel1
1GSG International GmbH, CH-8808 Pfäffikon, Switzerland
Corresponding Author: M. Frenzel, manfred.frenzel@gsg-int.com
Improvement of safety and security are important goals of γ-irradiation facility upgrades,
besides improvement of more economical and product quality related features. Safety of
γ-irradiators comprises three complexes which may require upgrades:
• Shielding of radiation when in operation and in stand by;
• Protecting people from entering or staying inside the irradiation room;
• Preventing of dispersal of radioactive material.
A more general problem with respect to safety is safety culture, which is on very different
levels at different places in the world. This is not limited to radiation protection but is a
problem also in other fields of commercial and daily life (road traffic, electricity, health and
safety at work). Here “upgrades” may be required as well.
Fortunately, respect from radioactivity increases safety attitude, at least at the beginning.
Limiting factors not only for upgrades but sometimes also for the safety level of new
installations are:
• Lack of financial resources;
• Lack of know how;
• Lack of safety culture;
• “cheap – cheaper – cheapest” business culture.
Security is all about preventing theft of radioactive sources for terroristic goals and other
abuse. Here it may be easier to overcome a possible lack of financial resources or of know
how due to the interest of the international community to eliminate terroristic threats.
IAEA–CN–241–357 153
A11
A11-02 Talk: Session A11, Thursday 09:20 Schmitz
Safety Improvements of an Industrial Irradiation Facility
F. Schmitz1
1Bel V, 1070 Anderlecht, Belgium
Corresponding Author: F. Schmitz, frederic.schmitz@belv.be
The operational experience feedback is a powerful tool to implement corrective actions after
an incident. These corrective actions, discussed and adequately defined with the regulator,
consist in a powerful way to improve the safety of a facility.
Belgiumhosts two 60Co industrial irradiators that have nowbeen used formore than 30 years.
During this period, the facility dealt with a few incidents that have driven improvements
through implementation of adequate corrective actions in the existing design and processes.
The licencee promoted transparency towards the regulator (Bel V and the FANC) and
declared all technical events related to safety and radioprotection. The licencee has proposed
technical and organizational solutions that were reviewed independently by Bel V to avoid
the recurrence of similar incidents. Short term improvements were immediately set-up after
the incidents. Mid-term improvements were also implemented. For more complex issues
such as the removal of broken sources, a long term planning was established, requiring the
participation of a large number of stakeholders: transport, safety authorities, waste disposal
facility, etc. For this type of issue a long term approach was favoured.
The will of the licencee to declare incidents to safety authorities and to implement adequate
corrective actions in agreement with the safety authorities, allows a regular improvement
of the facility in order to keep it up to date with safety standards and best practices.
This proactive management of incidents and corrective actions has also strongly increased
the safety culture awareness of the operators.
154 IAEA–CN–241–418
A11
Alcerreca Talk: Session A11, Thursday 09:40 A11-03
Upgrading and Continuous Improvement of ININ γ-Irradiation
Facility
M. Alcerreca1
1Instituto Nacional de Investigaciones Nucleares (ININ), La Marquesa Ocoyoacac, Mexico
Corresponding Author: M. Alcerreca, miguel.alcerreca@inin.gob.mx
The highlights of the updated activities at the ININ γ-irradiation plant facilities and im-
provements as well as in the irradiation process, tomake it a multipurpose plant with greater
capacity for products processing are shown in this work. The ININ γ-irradiation plant has
a 6500 JS irradiator originally designed for processing medical disposables. Since its start in
1980, the irradiation plant has been increasing their annual hours of operation and as a result
their number and diversity of clients from the food industry, pharmaceutical companies,
medicines and medical devices manufactures and health care products, to such an extent
that by the year 2000 and 2011 had seen the start of operations in the country, respectively,
of two new irradiation facilities from private capital. The importance of implementing and
maintaining a certified quality management system, improving ergonomics, establishing a
preventive maintenance system and critical spare parts inventory, maintaining the operating
licence as a result of good radiation safety practices, and good customer relationships to
support compliance with their regulations are remarked. Results are also presented in
improved uniformity of dose delivery, dose catalogue offered to clients, 60Co reloads (with
corresponding activities) and annual processing capacity obtained.
IAEA–CN–241–325 155
A11
A11-04 Talk: Session A11, Thursday 10:00 Mouhib
Enhancing Nuclear Security System of Irradiation Facility SIBO
INRA/Tangier Morocco
M. Mouhib1, M. Chentouf1, and A. Guessous2
1Institut National de la Recherche Agronomique (INRA), Tanger, Morocco
2University of Ibn Tofail, Kenitra, Morocco
Corresponding Author: M. Mouhib, momouhib@yahoo.fr
Around the world, radioactive sources have been widely used for decades to benefit hu-
mankind— to diagnose and treat illnesses, monitor oil wells and water aquifers, irradiate
food to eliminate microbes, andmany other uses. However, the malicious use of radiological
sources poses a significant threat globally. As irradiation facility for research, the goal of
this paper is to show a case study of application of nuclear security and nuclear security
culture code of contact in irradiation facility using 60Co. We will show the necessary work
done to achieve the goal protecting the radioactive material and continue working in safe
conditions. This objective could not have been achieved without the collaboration of all
departments involved in security and nuclear safety.
In all irradiation facility in the world the level of this control is always implemented to
achieve safety procedures in usual work on this field. In this work we applied the nuclear
security and nuclear security culture procedures in order to define the type of system used
to achieve the global objective in accordance with Global Threat Reduction Programme to
reduce the threat of a radiological dispersion device (RDD) in collaboration with the US
Department of Energy’s National Nuclear Security Administration (NNSA).
This work has been done with other operation in the same facility as local upgrading of 60Co
in our irradiator in Tangier and upgrading of safety and technical system of the irradiator
made in collaboration with IAEA, detail of this works are presented in others scientific
papers.
The objective of this paper is to share a local experience in upgrading security with return
of experience in practice and very good collaboration with general direction of national
security and all departments involved in security and nuclear safety
156 IAEA–CN–241–224
A11
Yu Talk: Session A11, Thursday 10:20 A11-05
Development and Application of Electron Linear Accelerator of
CIAE
G. Yu1, Z. Zeng1, Z. Zhu1, L. Zhang1, J. Li1, and J. Yang1
1China Institute of Atomic Energy (CIAE), Beijing 102413, People’s Republic of China
Corresponding Author: G. Yu, 13718666180@163.com
As an artificial radiation source, the electron linear accelerator is not only widely used
in basic science research, but also more and more used in industry, agriculture, medical
and environmental protection and other fields. The CIAE began to engage in research and
development of electron linear accelerators from its early establishment, and has converted
the research outcomes successfully into products and services in the cause of China’s
prosperously development.
These outcomes are mainly divided into two categories. The first category is the non-
destructive testing (NDT) electron linear accelerator (LINAC). In the 1990s, CIAE success-
fully developed China’s first NDT electron LINAC, then successively developed a series of
accelerator products with different X-ray beam energy like 2 MeV, 4 MeV, 6 MeV, 9 MeV, the
detection thickness of equivalent steel reach to 380 mm, mainly used in the verification of
weld joints of thick-walled pressure vessels, pipes, boilers, valves equipped in petrochem-
ical industry, thermal power plant and nuclear power plant, testing of the defect of key
components of the high-speed train, rocket engine and so on. The national standards of
NDT electron LINAC was drafted by CIAE and the corresponding international standard
project launched to International Electro-technical Commission (IEC) from CIAE has been
started and is progressing well.
The second category is electron LINAC for radiation processing. The first radiation facility
based on high-power high-energy electron LINAC developed by CIAE was put into trial
operation in 2007. The electron beam (EB) energy of this accelerator is 10 MeV, and the
power exceeded 15 kW, which was the highest power of the same type around that time.
Currently, the EB power of this type has reached 20 kW, and was capable of stable operation.
Number of radiation processing enterprises has purchase this type of accelerators, which
are used for garlic, tea preservation and pet food, seasoning sterilization.
In China, R&D direction of NDT electron LINAC is miniaturization and digitalization, while
for irradiation accelerators, scientists and engineers are striving to improve the EB power or
X-ray-conversion efficiency.
IAEA–CN–241–183 157
A11
ICARST–2017
A12:Radiation for Environmental Protection II
158
A12
Cabo Verde Talk: Session A12, Thursday 11:15 A12-01
Virucidal Potential of γ-Radiation
S. Cabo Verde1, A. Pimenta1, D. Guerreiro1, J. Madureira1, and F. Margaça1
1Instituto Superior Técnico (IST), Lisbon, Portugal
Corresponding Author: S. Cabo Verde, sandracv@ctn.tecnico.ulisboa.pt
Enteric viruses are a major cause of water- and food-borne human diseases. These type of
viruses primarily infect the intestinal tract through ingestion of contaminated water or food.
Enteric viruses, like norovirus (NoV) and adenovirus (AdV), can enter the environment
through the discharge of waste materials from infected individuals and be transmitted back
to susceptible individuals. The stability of these viruses and their presence in water and
food can thus cause serious implications on public health. In this scenario, γ-irradiation
could be an efficient technology to achieve elimination of viral pathogens.
The goal of this studywas to investigate the inactivation by γ-irradiation ofmurine norovirus
type 1 (MNV-1), as a NoV surrogate, and human adenovirus type 5 (AdV-5) in six different
aqueous substrates and two types of fresh berry fruits. Phosphate buffer saline (PBS),
demineralized water, tap water, fetal bovine serum (FBS) and aqueous solutions of 10% and
50% FBS as well as fresh strawberries and raspberries, were inoculated either individually
with MNV-1 and AdV-5 or with a viral pool of both viruses. The spiked samples were
irradiated in a 60Co chamber at several doses, 0.87 up to 11.35 kGy, at a dose rate of
1.6 kGy/h. For fresh berries samples, the viruses were recovered from spiked samples
and then purified and concentrated by low speed centrifugation. The infectivity of viral
particles of MNV-1 and AdV-5 was tested by plaque assay using Raw 264.7 and A549 cells,
respectively. D10 values and virucidal efficiency of γ-irradiation were estimated for each
virus and substrate.
A reduction on MNV and AdV titers of 4 log10 PFU/ml was achieved after irradiation at
3 kGy on PBS, demineralized and tap water suspensions. However, it was found that MNV-1
and AdV-5 were approximately 3 times more resistant to γ-radiation when irradiated in FBS
suspensions. Concerning the obtained results for fresh berries, a reduction on MNV-1 and
AdV-5 titers of 2 log10 PFU/g was achieved after irradiation at a dose of 4 kGy. Non-linear
inactivation survival curves were obtained for both virus in fresh berries, leading to the
detection of infective viral particles at a dose of 11 kGy.
MNV and AdV indicated to have the same radioresistance when irradiated in a viral pool or
in individual viral suspension for all tested matrices. The viral inactivation by γ-radiation
was found to strongly depend on the substrate where the viruses are suspended. The
study of viral behaviour in different substrates could open new insights on the inactivation
mechanism caused by γ-irradiation. The selection of the γ-radiation dose for the disinfection
treatment of berry fruits, must achieve the balance to guarantee food safety and preserve
food quality. The irradiation process presented virucidal potential. This technology can be
an effective virus mitigation tool to treat polluted waters, which are the major vehicle of
contamination for minimally processed food products.
IAEA–CN–241–147 159
A12
A12-02 Talk: Session A12, Thursday 11:35 Mezyk
Removal of Wastewater Pharmaceutical Chemical Contaminants
Using AOPs
S. Mezyk1
1California State University, Long Beach, Long Beach, CA 90840, USA
Corresponding Author: S. Mezyk, stephen.mezyk@csulb.edu
Quantitatively removing all remaining traces of pharmaceuticals such as antibiotics and
estrogenic steroids from effluent wastewater is essential before its further use or release
into the environment. In particular, the presence of antibiotics and even their metabolites
in wastewaters can enhance the proliferation of antibiotic-resistant bacteria such as MRSA
and ND-1. Unfortunately, conventional primary and secondary water treatments that
rely mainly upon adsorptive and chemical-physical processes have been demonstrated
to be insufficient for quantitative large-scale treatment. These removal treatments are
considerably complicated by the presence of much higher levels of other water constituents
such as dissolved organic matter (DOM) and carbonate.
Therefore, to prevent increasing levels of antibiotics entering environmental waters, ad-
ditional treatment using radical-based, advanced oxidation processes (AOPs), are being
considered to augment our traditional water treatments. In real-world waters most AOPs
utilize the hydroxyl radical (HO‚), which can be created using a variety of techniques
including combinations of ozone, hydrogen peroxide and UV-light: O3/H2O2, O3/UV-C,
and H2O2/UV-C. Other AOPs that produce a mixture of reducing and oxidizing radicals
include the light irradiation of titanium dioxide, sonolysis, or the irradiation of water via
electron beams or γ-rays. Once these radicals are generated, the dissolved oxygen present
will predominately react with the reducing hydrated electron or hydrogen atoms produced.
However, the deliberate addition of a compound such as persulfate to these waters can aug-
ment HO‚ reactions through the concomitant production of the sulfate radical (SO´‚4 ) by the
reaction of both these two reducing radicals. While this is a promising enhancement in the
AOP treatment methodology the effectiveness of the sulfate radical augmentation approach
must be fully established before its use at large scale. In particular, the cost-effectiveness
of this approach will depend upon the reactivity of the sulfate radical with other water
constituents.
Therefore, we have performed electron pulse radiolysis measurements to determine reaction
rate constants for hydroxyl and sulfate radicals with a large number of DOM fractions from
various sources. The sulfate radical rate constants were found to be effectively independent
of the DOM aromatic/aliphatic constituent fractions, and in general about an order of
magnitude slower than determined for the analogous HO‚ radical reactions. The slow
reactivity of the sulfate radical with DOM is encouraging, as it would allow a greater fraction
of these radicals to react with the contaminants present at much lower concentrations. To
further investigate this, we have also now performed preliminary measurements on the use
of sulfate radicals to remove low-levels of β-lactam antibiotics in the presence of different
DOM species. Kinetic and efficiency data for penicillin-G in the presence of varying ratios
of Suwannee River fulvic acid and Elliot Lake humic acid have been determined and will be
reported.
160 IAEA–CN–241–378
A12
Wu Talk: Session A12, Thursday 11:55 A12-03
Applications of Radiation Technology in Control and Treatment
for Environmental Pollution
M.-H. Wu1
1Shanghai University, Shanghai Shi, People’s Republic of China
Corresponding Author: M.-H. Wu, mhwu@shu.edu.cn
Radiation technology including electron beam and γ-ray irradiation has great potential in
the field of environmental protection due to its special characteristics. The investigations
and applications of radiation technology in the treatment of wastewater, waste gas and
solid waste are introduced in this paper, including the treatment of printing and dyeing
wastewater, paper mill wastewater, nitroanilines, halogenated flame retardants, endocrine
disrupting chemicals, algal toxin, volatile organic contaminants and sludge, etc., and the
removing of SOx andNOx in coal-fired and automobile exhausts. The degradation efficiency
of these organic pollutants by electron beam or γ-ray radiolytic degradation is discussed
in various conditions, such as different initial concentrations, irradiation doses, pH values,
solvents, radiolysis systems and the addition of H2O2, etc. Besides, the radiolysis products
of certain pollutants are listed and radiolytic degradation mechanisms of these organic
pollutants are illustrated. These results demonstrate that radiation technology is an effective
method to degrade the organic contaminants, especially the persistent organic pollutants,
hydroxyl radicals and hydrate electrons play significant roles in the radiolysis of organic
pollutants. In addition, the limitations and the future tends of radiation technology applied
in the environmental protection are also discussed.
IAEA–CN–241–127 161
A12
A12-04 Talk: Session A12, Thursday 12:15 Cha
Application of Mobile Electron Beam for Remediation of Soil
and Groundwater Contaminated with Leachate from Animal
Carcass Burial Sites
S. M. Cha1, T.-H. Kim1, H. Y. Kim1, K. Lee1, B. Shim1, J. I. Kim1, and S. Yu1
1Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
Corresponding Author: S. M. Cha, smcha@kaeri.re.kr
Leachates of livestock burial sites have raised a concern regarding their potential impact on
the environment and public health in Korea. They contain high concentrations of organic
and inorganic contaminants, and pathogenic microorganisms such as Campylobacter jejuni,
Salmonella spp., Clostridium perfringens, and Shigella spp. Several studies have attempted
to remove contaminated groundwater by leachates, but an effective method has not been
found. Thus, the objective of this study was to treat leachates from livestock burial sites
using a combined process of pretreatment and an electron beam. The pretreatment system
consists of two columns: activated carbon and zeolite. Leachates used in this study were
collected from groundwater near a livestock burial site located in Gyeonggi-do, Korea. The
removal efficiencies of suspended solids and total organic carbon were 98% and 77% by
an activated carbon process, respectively. NH3-N was removed about 80% through the
zeolite process. In addition, microorganisms showed a removal efficiency of 99.99% using
an electron beam at an absorbed dose of 2 kGy. Consequently, the combined processes
of pretreatment and an electron beam can be applied to the remediation of groundwater
contaminated by leachates.
162 Presenter: S. Yu IAEA–CN–241–163
A12
Batchelor Talk: Session A12, Thursday 12:35 A12-05
Electron Beam Treatment for Potable Water Reuse: Removal of
Bromate and Perfluorooctanoic Acid
B. Batchelor1, S. Pillai2, L. Wang1, and V. S. Botlaguduru1
1Texas A&M University, College Station, TX 77840, USA
2National Center for Electron Beam Research, College Station, TX 77845, USA
Corresponding Author: B. Batchelor, bill-batchelor@tamu.edu
Water availability is a major problem facing many regions around the world. To meet
growing residential and agricultural needs, effective technologies have to be adopted to
address microbial and chemical contaminants as part of water reuse programmes. The
underlying hypothesis was that electron beam (EB) technology can breakdown the emerging
contaminants of concern in water reclamation and reuse projects. We also hypothesized
that the inactivation and elimination of contaminants by EB technology can be achieved
cost-effectively. Having this technology in the “tool-box” of water reclamation technologies
would open up innovative high-value, commercially-viable, and environmentally sustain-
able solutions and strategies for water reuse.
In this study, EB irradiation was investigated as a method for removing bromate and perflu-
orooctanoic acid (PFOA) from a synthetic water designed to simulate a treated wastewater
intended for potable water reuse. In the absence of oxygen, an exponential model was
able to relate bromate concentration to absorbed dose. However, a more complex model
was needed to describe PFOA defluorination, so a model was developed that assumed
formation of one partially defluorinated intermediate and this model was used to describe
the relationship between free fluoride concentration and absorbed dose. Nitrate negatively
affected the removal of bromate and the dose constant was inversely proportional to the
nitrate concentration as predicted by a simple model that assumes the presence of radical
scavengers. In contrast, the presence of nitrate improved the degradation of PFOA, possibly
due to formation of oxidizing radicals or by other reactions of nitrate degradation products.
Fulvic acid and alkalinity exerted negligible influences on bromate removal. Fulvic acid
dampened the defluorination efficiency, probably due to the scavenging of oxidizing radicals
such as the hydroxyl radical (‚OH). Alkalinity was found to accelerate PFOA defluorination,
possibly because of the formation and reactivity of the carbonate radical (CO´‚3 ). As pH
increased from 5.0 to 7.3, the dose constant for bromate removal increased from 0.45{kGy
to 0.69{kGy, but it barely changed when pH was further increased to 9.0. In the presence
of oxygen, both contaminants were degraded less efficiently and showed more complex
patterns of degradation. Pretreatment to remove dissolved oxygen would probably be
needed to apply EB in practice for degradation of bromate and PFOA.
IAEA–CN–241–228 Presenter: S. Pillai 163
A12
A12-06 Talk: Session A12, Thursday 12:55 Sági
Changes in the Biological Degradability and Toxicity of
Sulfonamide Antibiotics in Activated Sludge and River Water
due to Ionizing Radiation Treatment
G. Sági1, A. Bezsenyi2, K. Kovács1, S. Klátyik3, B. Darvas3, A. Székács3, L. Wojnárovits1,
and E. Takács1
1Hungarian Academy of Sciences Centre for Energy Research, Budapest, Hungary
2Budapest Sewage Works Pte Ltd., South-Pest Wastewater Treatment Plant, Budapest, Hungary
3Agro-Environmental Research Institute, National Research and Innovation Centre, Budapest, Hungary
Corresponding Author: G. Sági, sagi.gyuri@energia.mta.hu
During conventional wastewater treatment, the removal of pharmaceutical compounds is
usually inadequate as most of the xenobiotics show high resistance to biological decompo-
sition by activated sludge. This deficiency can be counteracted by application of ionizing
radiation treatment that leads to oxidation of organic molecules mainly by reactions of
hydroxyl radicals. Oxidation may result in a complete solution to the final disposal of
pollutants with no further purification steps required, but may also contribute to formation
of biodegradable, less harmful transformation products.
The biodegradability and toxicity have been examined on 10´4 mol{dm3 sulfonamide antibi-
otic solutions with considerably different chemical structure (sulfanilamide, sulfaguanidine,
sulfathiazole and sulfamethoxazole) and their products at different stages of oxidative
decomposition. The biodegradability in activated sludge and freshwater has been specified
by the ratio of the biological and chemical oxygen demand (BOD/COD), while the toxic
properties have been evaluated by activated sludge respiration inhibition tests and acute
toxicity experiments done on Vibrio fischeri, Pseudokirchneriella subcapitata andDaphnia magna.
Test organisms were placed under the exposition of same loads of test substances and the
interfering effects of H2O2 forming during irradiation procedure have been eliminated.
Initial sulfonamide solutions inoculatedwith activated sludge showed lowBOD/COD (0.16–
0.21), while complete resistance has been observed when river water was used as inoculum.
The biodegradability continuously increased as a function of absorbed dose in both matrices
and ready biodegradability (BOD/COD „ 0.7) has been reached at 1.5 kGy and 2.0 kGy
in case of activated sludge and river water, respectively. This difference in absorbed doses
means that higher degree of oxidation is needed, when sulfonamides are subjected to river
water community, to achieve same biodegradability level under same time as in case of
activated sludge. Nevertheless, already a few tenth kGy of absorbed dose led to increment
in biological availability. Activated sludge respiration inhibition tests showed no toxic effects
of both initial and treated solutions. Growth inhibition on Pseudokirchneriella subcapitata has
been reduced during treatment. Vibrio fischeriwas susceptible to treated solutions, as the
inhibition increased in case of sulfamethoxazole and sulfathiazole. Mortality of Daphnia
magna considerably reduced in treated solutions, with the exception of early products of
sulfathiazole.
It can be concluded that biological treatment at conventional wastewater treatment plants is
not adequate for removal of sulfonamide antibiotics. Nevertheless, ionizing radiation led to
formation of products biologically degradable by activated sludge.
164 IAEA–CN–241–243
A12
ICARST–2017
A13:Advanced Nano Materials
165
A13
A13-01 Talk: Session A13, Thursday 16:30 Dispenza
Radiation Synthesis of Nanosized Drug Delivery Devices
C. Dispenza1
1Università degli Studi di Palermo, Palermo, Italy
Corresponding Author: C. Dispenza, clelia.dispenza@unipa.it
The radiation chemistry of polymer aqueous solutions is a successful synthetic methodology
for large scale production of nanosized drug delivery systems. That is particularly true for
nanogel drug carriers. Nanogels are fascinating nanoparticles that, for their tunable chemical
structure and swelling ability by water molecules, can be designed to be biocompatible,
to offer conformable cavities to incorporate bulky therapeutic proteins, but also small
hydrophobic pockets to host barely polar molecules, which is the case of most medical
drugs. They can display reactive groups to conjugate targeting ligands, such as monoclonal
antibodies, peptides and oligonucleotides. These nanoparticles can be used to target specific
cells and cellular microenvironments with high specificity and affinity. They can also
incorporate chelating agents that bind radioactive ions, either for bio-imaging or therapeutic
purposes. The possibility of producing nanogels as aqueous dispersions, without going
through a drying step for purification since no recourse to organic solvents and surfactants
is made, is the best guarantee for preserving their size, hence functionality.
Water radiolysis provides a means of generating initiating radicals at the desired rate. These
radicals can either recombine or react with the polymer solute, transforming the other-
wise chemically inert macromolecule into multiradical species. Radicals formed on the
polymer can either react with molecular species present or formed in solution, or com-
bine with other macroradicals. Intramolecular combination creates permanent loops and
cross-linking points within the same chain, transforming the linear or branched polymer
chain into a nanoscalar network. Intermolecular combination, binding polymer chains
together, contributes to increase the nanogel size and molecular weight. By tuning the
irradiation conditions we expect to be able to tailor both particle size and chemical composi-
tion. In order to establish relevant process-structure-property relationships, irradiations
are performed with pulsed electron beams varying the irradiation conditions and system
composition. The efficiency of the polymer in scavenging the initiating radicals is estimated.
The produced nanogels are characterized for their composition and particle size. The pos-
sibility of generating nanogels with controlled hydrodynamic diameter in the range from
20 to 200 nm and relatively narrow particle size distributions (PDIă0.3) is demonstrated.
Irradiation conditions that favour intra-molecular cross-linking are identified, the most
important parameter to control being the polymer molar concentration. Functional groups
are generated on the polymer by the reaction of some macroradicals with molecules that
may be produced in situ by irradiation (e.g., H2O2, O2) or purposely added to the system
(unsaturated monomers). These groups are used to bind therapeutic biomolecules, that can
be protected by the nanogel from degradation when in solution and be exposed to their
receptors when the nanoparticles experience a change in their microenvironment (e.g., at
the cell membrane).
The easy of manufacture and purification of the base nanogels, the possibility to use them
as substrates for different therapeutic strategies by attaching specific ligands and drugs,
and their properties when evaluated in relevant cellular and animal models represent today
a very promising prospect for translation into clinical use.
166 IAEA–CN–241–281
A13
Grasselli Talk: Session A13, Thursday 16:50 A13-02
Protein-Based Nanoparticles Prepared by Radiation-Induced
Cross-Linking
M. Grasselli1, E. Achilli1, C. Y. Flores1, M. Siri1, and S. D. V. Alonso1
1UNQ-IMBICE-CONICET, Buenos Aires, Argentina
Corresponding Author: M. Grasselli, mariano.grasselli@unq.edu.ar
The powerful of ionizing radiation of electron beam or γ-sources to cross-link polymers has
been largely demonstrated. Preparation of cross-linked hydrogels for wound dressing by
this technique has important advantage to other chemical process. In addition, ionizing
radiation technology has the ability to generate intermolecular or intramolecular cross-
linking. Conversely, for several decades have been demonstrated that irradiation of protein
solutions generates mainly degradation products. Only protein solutions in frozen state
can be sterilized by γ-rays avoiding protein degradation.
Low amounts of polar solvents can be added to protein solutions without produce denatu-
ration. By dynamic light scattering (DLS) it is possible to follow the protein aggregation
process in solution; however, this effect is reversible. In this work, novel methods of Albumin
NPs (Alb NPs) and core/shell gold/Albumin NPs (Au/Alb NPs) preparations are shown
by radiation induced cross-linking.
Albumin dissolved in ethanol/water solutions were irradiated with ionizing radiation
sources (γ-rays or electron beam). In both cases NPs were obtained after irradiation with
at least 2 kGy r1, 2s. NP size can be modulated with the ethanol concentration. In the
same way, core/shell Au/Alb NPs has been prepared by a similar technique. In this case a
multilayer of cross-linked Albumin coated the Au NPs.
NPs were characterized by different techniques such as DLS, UV-visible and infrared spec-
troscopy, transmission electron microscopy and atomic force microscopy. NPs sizes were
in the range of 20–40 nm for Alb NPs and 60–80 nm for Au/Alb NPs. In the last case,
TEM images showed that the NPs have spherical shape and the presence of a low-density
halo around the metal core confirms the presence of Albumin. Using an antigen-antibody
recognition analysis was able to demonstrate the biospecificity of the NPs surfaces.
References
r1s S. L. S. Espinoza, et al., Radiat. Phys. Chem., 81, 1417–1421 (2012).
r2s E. Achilli, et al., Coll. Surf. A, 486, 161–171 (2015).
IAEA–CN–241–295 167
A13
A13-03 Talk: Session A13, Thursday 17:10 Pasanphan
Molecular Design and Synthesis of Different Polymer-Based
Nanoparticles as Nanocarriers Using Irradiation Techniques
W. Pasanphan1, T. Rattanawongwiboon1, E. Haujaikeaw1, and T. Piroonpan2
1Department of Materials Science, Kasetsart University, Krung Thep Maha Nakhon 10900, Thailand
2Department of Imaging and Printing Technology, Chulalongkorn University, Bangkok, Thailand
Corresponding Author: W. Pasanphan, wanvimol.p@ku.ac.th
Significant progress has been made during the past decade in preparing polymer-based
nanoparticles (NPs) as nanocarriers for a wide range of applications. One of the next
critical challenges is developing a green, robust and versatile method using irradiation
techniques which allows the synthesis of different polymer nanoparticles into functional
structures tailored for each specific purpose. In this work, we proposes the molecular
design and irradiation-assisted synthesis for the creation of polymer-based nanostructures,
i.e., amphiphilic polymer core-shell NPs, inter-polymer complex NPs, polymer-capped
metal NPs and hydrid NPs to be applied as nanocarrier for drug delivery, agrochemical
entrapment, paint and coating additives. According to the different molecular structures,
radiation-induced degradation, grafting and polymerization were carried out in particular
water-based system at room temperature. Subsequent γ-ray and electron beam irradiation
doses ranging from 5 to 100 kGy were selected and controlled to achieve nanocale structure
with the size of 10–300 nm. The amphiphilic core-shell water-soluble chitosan NPs („
120 nm) could encapsulate Berberine and Paclitaxel anticancer drugs with the drug content
of 37% (w/w). Chitosan-polyacrylic acid interpolymer complex NPs (54 nm) efficiently
entrap 20% (w/w) ammonium nitrate fertilizer and exhibit pH responsive function. Gold
nanoparticle (5–50 nm) was successfully green synthesized in the water-soluble chitosan
(WSCS) produced from radiation-induced degradation. In addition, electron beam can
also accelerate the production of AuNPs in WSCS. The polymer brush shells were grafted
onto silica NPs and silver NPs (5 nm) were then constructed on the polymer brush-grafted-
silica NPs (98 nm). The obtained hybrid NPs effectively inhibited the growth of building
fungi, i.e., Spergillus Niger and Syncephalastrum Racemosum. All types of polymer-based
nanoparticles with different functions were successfully designed and prepared using
irradiation techniques.
168 IAEA–CN–241–143
A13
Katti Talk: Session A13, Thursday 17:30 A13-04
Green Nanotechnology in Nuclear Medicine: Tumor Specific
Radioactive Gold Nanoparticles for New Approaches in Cancer
Therapy
K. V. Katti1
1Department of Radiology, University of Missouri, Columbia, MO 65211, USA
Corresponding Author: K. V. Katti, kattik@health.missouri.edu
We report herein, for the first time, on the application of Mangiferin—a glucose function-
alized xanthanoid found in abundance in mango peel—as a tumor targeting agent for
the selective delivery of inherently therapeutic radioactive gold nanoparticles (198Au) into
prostate tumors in mice. Mangiferin functionalized radioactive gold nanoparticles (MGF-
198AuNPs) have been synthesized and fully characterized for their potential applications
in tumor therapy. The highly innovative feature of this green nanotechnology focussed
work is the ability of Mangiferin to serve dual roles of chemical reduction, to produce gold
nanoparticles, with subsequent encapsulation to afford in vivo stability and tumor specificity.
Laminin receptor specificity of Mangiferin affords site-specific accumulation of optimum
therapeutic payloads of this new therapeutic agent within prostate tumor cells (PC-3) of hu-
man prostate tumor origin. Over expression of laminin receptors in human prostate tumors
and the selective affinity of Mangiferin toward such receptor subtype has allowed effective
treatment of prostate tumors in mice using the new MGF-198AuNPs— thus demonstrating
that small sized phytochemicals will play important roles in achieving tumor specificity
in drug design. The dual β and the γ-emissions of 198Au provides unique advantages for
tumor therapy, through the β-energy while γ-rays are used for the quantitative estimation
of gold within the tumors and various organs through radio scintigraphy. Detailed in vivo
therapeutic efficacy studies, through the intratumoral delivery of MGF-198AuNPs, revealed
that over 80% of the injected dose (ID) ofMGF-198AuNPswas retained in prostate tumors up
to 24 h. There was minimal to no leakage of MGF-198AuNPs to non-target organs including
liver, blood and stomach. This unprecedented retention of MGF-198AuNPs within prostate
tumors translated into excellent ability of this nanoceutical to reduce tumor volumes in com-
parison to saline control groups. By three weeks post-treatment, tumor volume of control
group (saline) was significantly lower than the tumor volume of the two different groups
of prostate tumor bearing mice injected with radioactive nanoparticles (1.31 ˘ 0.00 cm3
for control versus 0.18 ˘ 0.17 cm3 for MGF-198AuNPs for group 1, and 0.22 ˘ 0.02 cm3
for MGF-198AuNPs for group 2). Observation of normal blood parameters, body weights
and the overall systemic tolerance of MGF-198AuNPs, in both the experimental and control
groups, suggested new opportunities in oncology for the application of this agent for the
treatment prostate and various other tumors.
IAEA–CN–241–421 169
A13
A13-05 Talk: Session A13, Thursday 17:50 Varca
State of the Art and Current Advances on Protein Cross-Linking
by Irradiation: Protein Based Nanocarriers and Bioactive
Nanoparticles
G. H. C. Varca1, L. B. Mohamed1, G. N. Fazolin1, J. G. D. S. Batista1, R. G. Queiroz1,
A. B. Lugão1, F. A. Navarro Marques2, and A. H. Ferreira1
1Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), São Paulo, Brazil
2InRad, Escola de Educação Permanente HCFMUSP, São Paulo, Brazil
Corresponding Author: G. H. C. Varca, varca@usp.br
The highlighted role of protein and peptide based delivery systems relies upon the possibility
to develop biocompatible drug carriers featuring site specific delivery, biological affinity
among unique advantages. Recently, a technique for protein nanostructuring by the use
of radiation has been recently reported by our group. Advantages of the use of radiation
over conventional methods are related to the possibility to achieve protein cross-linking
and sterilization in a single step, as well as the capacity to allow the design of nanocarriers
without the need of monomers or toxic cross-linkers. This work reports the use of high
energy irradiation towards the design of size-controlled protein-based nanocarriers and
bioactive nanoparticles, using bovine serum albumin (BSA) and papain asmodel protein and
protease, respectively, including the state of the art and current advances of the technology.
The technique implies on protein desolvation/solvation techniques followed by cross-linking
by EB radiation or γ-irradiation alone, although nanoparticles were also achieved in absence
of the cosolvents. Size-controlled BSA nanocarriers were manufactured up to 80 nm and
papain bioactive nanoparticles up to 12 nm, as determined by dynamic light scattering.
Nanocarrier morphology was evaluated by and negative staining transmission electron
microscopy. Protein cross-linking and changes in aromatic the amino acids were evaluated
by fluorescencemeasurements. Biocompatibility experimentswere also performed bymeans
of cytotoxicity and cytokines production. The potential of the systems for the delivery of
radiopharmaceuticals or chemotherapeutic agents were also assayed, using technetium or
Paclitaxel respectively. In conclusion, the technique allowed the production of biocompatible
and bioactive protein nanoparticles suitable for the administration of radiopharmaceuticals
and chemotherapeutic agents.
170 IAEA–CN–241–408
A13
Bondar Talk: Session A13, Thursday 18:10 A13-06
Radiation-Chemical Synthesis of Nanocomposite Adsorbents
Based on Polypropylene Fibres for Selective Removal of Heavy
Metals and Radionuclides
Y. Bondar1, D. H. Han2
1Institute of Environmental Geochemistry, Kiev-142, 03680, Ukraine
2School of Chemical Engineering and Technology, Yeungnam University,
214-1 Dae-Dong, Gyeongsan 712-749, Republic of Korea
Corresponding Author: Y. Bondar, juliavad@mail.ru
Polypropylene (PP) fibres are widely used in sorption processes. The range of their possible
applications can be extended by modification with the use of radiation-induced graft poly-
merization method. This method allows grafting of nano-microchains of a vinyl monomer
with a desired functional group onto the inert surface of PP base, ensuring control over
the length and density of the grafted chains. The resulted material consists of two parts:
the polymeric base and the chemically bound chains with functional groups (ion-exchange
or chelating), and so it can be used as polymer adsorbent. In the past decades, fibrous
polymer adsorbents have been considered as potential alternative to granular ion exchange
resins because of their high adsorption parameters. Numerous adsorbents on the base of
PP fibres have been synthesized, but only a few of them could be adjusted for selective
removal of pollutants from water effluents because of limited variety of available functional
groups. In recent years, hybrid adsorbents (polymer/inorganic nanoparticles) have been
developed as a new class of adsorption materials. They were fabricated mostly by the in situ
formation of inorganic nanoparticles or by incorporation of preliminary formed inorganic
nanoparticles into voids of macroporous ion exchange resins. Although polymer fibres
are very attractive support in preparing hybrid adsorbents, there are only a few publica-
tions on this theme. The considered research was focussed on the fabrication of novel
hybrid adsorbents based on the polypropylene fibres coated with inorganic nanoparticles
for selective removal of heavy metals and radionuclides. The hybrid adsorbents were syn-
thesized through a two-stage experiment: radiation-induced graft polymerization of a vinyl
monomer with functional group (ion-exchange or chelating) onto the PP fibres’ surface,
followed by the in situ formation of inorganic nanoparticles within the grafted chains. For
selective removal of radionuclides from contaminated waters (natural or industrial origin)
4 types of hybrid adsorbents based on grafted polypropylene fibres have been synthesized:
PP fibres coated with ferrihydrite (iron hydroxide) nanoparticles; PP fibres coated with
manganese hydroxide; PP fibres coated with K-Ni and K-Cu hexacyanoferrate; PP fibres
coated with hydroxyapatite nanoparticles. FT-IR-ATR, and X-ray diffraction techniques
confirmed the formation of inorganic nanoparticles on the PP fibres surface. SEM study
revealed that nanoparticles form a homogeneous layer of nanosized aggregates which are
regular in shape and pack closely forming a compact texture on the fibre surface. Syn-
thesized composite fibres were found to be stable in aggressive solutions for long times.
The targeted radionuclide adsorption on the composite fibres was studied as a function
of contact time, pH, initial ion concentration and the presence of competitive ions. The
synthesized adsorbents demonstrated fast adsorption kinetics, high adsorption capacity and
high selectivity. The proposed strategy of the nanocomposite fibre synthesis opens ample
opportunities for the fabrication of adsorbents, catalysts, biochemical and chemical sensors
on the base of commercially available polymer fibres, fabrics, resins and membranes.
IAEA–CN–241–206 171
A13
A13-07 Talk: Session A13, Thursday 18:20 Salih
Preparation of Polyurethane Acrylate/ Organically Modified
Montmorillonite Nanocomposites by Electron Beam Radiation
Curing
A. Salih1, M. Bin Ahmad2, N. A. Ibrahim2, K. Z. Hj Mohd Dahlan3, R. Tajau4,
M. H. Mahmood5, and W. M. Z. Wan Yunus6
1Department of Radiation Processing, Sudan Atomic Energy Commission, Khartoum, Sudan
2Department of Chemistry, University Putra Malaysia, Selangor, Malaysia
3Polycomposite Sdn BHD, Selangor, Malaysia
4Radiation Processing Technology Division,
Malaysian Nuclear Agency, Bangi, 43000 Kajang, Selangor, Malaysia
5No.107, Jalan 2, Taman Kajang Baru, Sg Jelok, 43000 Kajang, Selangor, Malaysia
6Department of Chemistry, National Defence University of Malaysia, Kuala Lumpur, Malaysia
Corresponding Author: A. Salih, ashraf.salih@gmail.com
The electron beam radiation curing of polyurethane acrylate (PUA)/montmorillonite (MMT)
modified by octadecylamine (ODA-MMT) nanocomposites was investigated in this article.
The nanocomposites were obtained and characterized by different techniques. The produced
nanocomposites, showed remarkable improvement in their mechanical and morphological
properties, compared to the pristine PUA. The XRD results revealed that the ODA-MMT
silicate interlayer spacing increased up to 3.9 nm, indicating the intercalation structure.
Whereas, the pristine MMT microcomposite showed agglomeration. The FTIR results
confirmed the intercalation of the PUA chains in the silicate layers, nevertheless, the chemical
structure of the PUA was not influenced by the presence of the silicate layers in the matrix.
The mechanical properties of the nanocomposites showed incredible increasing in the
modulus value, from 8.53 ˘ 0.40 to 132.43 ˘ 6.60 MPa by the dispersion of 5 wt% ODA-
MMT in the PUA matrix, as well as the tensile and the dynamic mechanical properties were
also improved. The radiation dose and the amount of the tri-functional monomer (TMPTA)
in the formula were affected significantly the cross-linking affect the cross-linking density
of the cured PUA nanocomposites.
172 IAEA–CN–241–197
A13
ICARST–2017
A14:Technical Cooperation Success Stories
173
A14
A14-01 Talk: Session A14, Friday 09:00 Mihaljević
Recent Radiation Research and Technology Development in
Croatia
B. Mihaljević1
1Ruđer Bošković Institute, Zagreb, Croatia
Corresponding Author: B. Mihaljević, mihozeg@irb.hr
TheRuđer Bošković Institute is Croatia’s leading scientific institute. TheRadiationChemistry
and Dosimetry Laboratory (RCDL) has remained until the present day the only unit in
the country pursuing both basic and applied scientific research in the fields of radiation
chemistry, dosimetry and radiation processing. Physico-chemical effects of irradiation,
being function of absorbed dose, are used for the quantitation of absorbed energy, i.e.,
dosimetry. Two families of liquid chemical dosimetry systems have been developed by the
RCDL. The low-dose system is nowadays one of the best characterized chemical dosimetry
systems in the range of therapy and accident doses. The high-dose system, based on the
ethanol-chlorobenzene (ECB), has been accepted as a joint ISO/ASTM 51538 standard.
Research in applied radiation chemistry and radiation microbiology, analyses of epidemi-
ologic and economic data, our presence on national and international bodies generating
and maintaining corresponding regulations, permanent improvements of our irradiation
facilities and other activities all have helped introduce into Croatia the necessary scientific,
technical, legal, economic and other prerequisites for technology transfer in the yield of
radiation processing. At present, RCDL has the only facility of its kind in Croatia and the
region. The main equipment is a batch type panoramic γ-irradiator (95 kCi 60Co) which has
been designed by the RCDL staff, and its periodical upgrading has been regularly assisted
by the IAEA. Although only an experimental facility at the beginning, it was designed
with the future role of a multipurpose pilot scale irradiation facility in mind, capable to
contain more than 100 kCi of 60Co. The irradiator is suitable for a variety of applications,
from medium dose range used in radiobiology to high doses used in radiation processing
and radiation chemistry. The capacity of the irradiator chamber is 4–6 m3 of material per
batch. There is no conveyor to transport goods into and out of irradiation chamber giving
maximum flexibility with respect to the dimensions and weight of the objects. Performing
commercial scale irradiation for sterilization, pasteurization, decontamination and disin-
festation of various materials such as medical supplies, pharmaceuticals, foods, cosmetics
and toiletries, packaging, etc., provided the necessary understanding of practical aspects
of irradiation processes and dosimetric control methods. In recent years the interest for
irradiation protection and conservation treatment of cultural artefacts has been strongly
increased and successfully carried out in Croatia and region.
In this lecture a review of scientific research and development of the RCDL over the past five
years will be presented, with special attention given to the recent upgrading of the facility.
This upgrading has enabled the RCDL to offer the exchange of knowledge and experience in
many areas of scientific research as well as to offer more extensive and diverse applications
of radiation technology.
The support of the IAEA in ensuring timely supplies 60Co over the years, especially through
the recent Technical Co-operation Project CRO/1/006 (2014-2015) is gratefully acknowl-
edged.
174 IAEA–CN–241–425
A14
Calvo Talk: Session A14, Friday 09:20 A14-02
Multipurpose γ-Irradiator and Mobile Unit with an Electron
Beam Accelerator Developed in Brazil
W. A. P. Calvo1, C. L. Duarte1, S. L. Somessari1, F. E. Sprenger1, F. E. Costa1, A. Feher1,
P. A. V. Salvador1, N. M. Omi1, L. G. A. Silva1, F. F. Lainetti1, P. R. Rela1, and
M. H. O. Sampa1
1Brazilian Nuclear Energy Commission (CNEN), Rio de Janeiro, Brazil
Corresponding Author: W. A. P. Calvo, wapcalvo@ipen.br
Radiation processing technology for industrial and environmental applications has been
developed and used worldwide in the fields of water treatment, advanced materials, nan-
otechnology, medicine, tissue engineering, disinfestations and disinfection of books and
documents, processes and industrial production and natural resources, among others.
The Radiation Technology Centre (RTC) of the Nuclear Energy Research Institute (IPEN),
of CNEN, Brazil, developed a small size continuous run and multipurpose industrial γ-
irradiatorwith a revolutionary design and national technology to be used as a demonstration
facility for manufacturers and contract service companies that need economical and lo-
gistical in-house irradiation system alternatives. It will be useful for supporting the local
scientific community for product and process development using γ-radiation, assisting the
traditional and potential users on process validation, and for training and qualification of
operators and radioprotection officers. The technology developed for this facility consists
of a continuous tote box transport system comprising a single concrete vault, where the
automated transport system of products in and out of the irradiator utilizes a revolving
door integrated with the shielding, avoiding the traditional maze configuration. Covering
76 m2 of floor area, the irradiator design is product overlap sources with a maximum 60Co
capacity of 37 PBq (tote boxes, Category IV, wet storage). The performed qualification
programme of this multipurpose irradiator was based on AAMI/ISO 11137 standard. The
irradiator currently holds 7.4 PBq (200 kCi) of 60Co. For irradiator dose optimization, the
source distribution was done using the Cadgamma software. The poly-methylmetacrylate
(PMMA) dosimeter system was used for irradiator dose mapping. The economic analysis
and performance, concerning to the dose uniformity and 60Co utilization efficiency were
calculated and compared with other commercial γ irradiators available in the market.
The RTC is involved in establishing a mobile electron beam accelerator unit to treat indus-
trial effluents for reuse purposes. The mobile unit will be equipped with an electron beam
accelerator (0.7 MeV, 20 kW) with safety requirements (BSS, IAEA and CNEN Safety Stan-
dards), and can be used for effluent treatment from petroleum production, for petroleum
desulfurization, and, in addition, for degradation of toxic organic compounds in wastewater
for reuse. This project is supported by the IAEA (TC Project BRA1035, 2016–2018) and by
the Brazilian Financial of Studies and Project (FINEP). To enlarge the national capacity to
treat industrial effluents using electron beam accelerators, the mobile unit treating efflu-
ents on site from 1 m3/h up to 1000 m3/day, will provide an effective facility between a
laboratory-scale plant to a large-scale plant, with the objective to demonstrate its efficacy
and to transfer the technology. Studies have taken place in various productive sectors
in the country and in other foreign laboratories to prove that radiation treatment offers
technological and economic benefits over conventional techniques for treating recalcitrant
pollutants.
IAEA–CN–241–458 175
A14
A14-03 Talk: Session A14, Friday 09:40 Lanuza
Radiation Processing in the Philippines: Developments and
Prospects
L. Lanuza1, A. Maningas1, G. F. Dean1, and H. Solomon1
1Philippine Nuclear Research Institute (PNRI), Quezon City, Philippines
Corresponding Author: L. Lanuza, lglanuza@pnri.dost.gov.ph
Radiation processing is the treatment by radiation to get the desired effects in the products.
It offers various advantages in the field of sterilization of medical products, food irradi-
ation and a treatment of a variety of products, which have direct relevance to industrial
productivity and healthcare.
Various R&D activities in the Philippines have been undertaken since 1965 by the Philippine
Atomic Energy Commission/Philippine Nuclear Research Institute (PAEC/PNRI), the
academic and other government research institutions utilizing the γ-irradiation facility
of PNRI and the recently established electron beam (EB) irradiation facility. These are
demonstration facilities to assess the techno-commercial viability of the processes such as
decontamination of spices, herbal products and cosmetic raw materials, food irradiation
and radiation sterilization of medical devices. The new areas being explored include the use
of EB-grafted non-woven fabrics as metal adsorbents and the use of modified carrageenan
as plant growth promoter. These studies strongly indicate that radiation processing has a
strong potential for technology transfer to Philippine industries.
This paper presents an overview of current developments in research activities and commer-
cial applications of radiation processing in the Philippines, the different radiation processing
facilities, the ongoing upgrading of the γ-irradiation facility to meet the demands of the
industry and the technology transfer activities currently being undertaken.
176 IAEA–CN–241–336
A14
Adu-Gyamfi Talk: Session A14, Friday 10:00 A14-04
Radiation Processing in Ghana: Achievements, Prospects and
Challenges
A. Adu-Gyamfi1
1Ghana Atomic Energy Commission (GAEC), Legon-Accra, Ghana
Corresponding Author: A. Adu-Gyamfi, adugyamfi21@yahoo.com
The Ghana Atomic Energy Commission (GAEC) commenced research and development
activities in the area of radiation processing in 1970 with a laboratory scale irradiator
through the assistance of the IAEA. The programme was facilitated by training of the
relevant scientific and technical expertise at the national level. In 1994, a semi-commercial
irradiator (Gamma Irradiation Facility, GIF) was installed by the Government of Ghana
with the assistance of the IAEA. The GIF was further upgraded in 2010 with funds from
the Export Development and Agricultural Investment Fund (EDAIF) to enable full-scale
commercial operation. The Ghana Standards Authority has developed two standards to
regulate radiation processing in the country. Currently the GIF provides irradiation services
to the agricultural, medical and export sectors of the economy notwithstanding further
emerging prospects in the agro-processing sector. The School of Nuclear and Allied Sciences
has developed a postgraduate programme in radiation processing to ensure a sustainable
requisite human resource base. Realistic mechanisms for public-private partnerships need
to be identified and implemented to assist with transfer of the technology of radiation
processing in the country. Continued support of the government, regional collaboration,
and strategic cooperation with the IAEA will be vital in the successful commercialization of
radiation processing technology.
IAEA–CN–241–428 177
A14
A14-05 Talk: Session A14, Friday 10:20 Prieto Miranda
Radiation Processing in Cuba: Past, Present and Perspective
E. F. Prieto Miranda1
1Centro de Aplicaciones Tecnológicas y Desarrollo Nuclear (CEADEN), Havana, Cuba
Corresponding Author: E. F. Prieto Miranda, efprieto@ceaden.edu.cu
In the present paper is shown the evolution of the radiation processing in Cuba and the
development reached until today and the perspectives, aswell as, the technical characteristics
of our radiation facilities, the results obtained with the application of this technology in
several branches of the science, like medicine, biology and agriculture, as much at research
scale as pilot projects. It will cover the most significant aspects related with the sterilization
of medical-pharmaceutical material, food irradiation, of biological products, modification
of materials, detection of irradiated foods, quality control management, dosimetric systems
employed in the process control and the regulatory aspects of radiation processing in our
country.
178 IAEA–CN–241–368
A14
Rangel Urrea Talk: Session A14, Friday 10:40 A14-06
Drafting and Preparation of Proposals of Irradiation Plants:
Mexico Experience
J. W. Rangel Urrea1, L. C. Paredes-Gutierrez1
1Instituto Nacional de Investigaciones Nucleares (ININ), La Marquesa Ocoyoacac, Mexico
Corresponding Author: J. W. Rangel Urrea, walter.rangel@inin.gob.mx
The drafting, integration and evaluation of infrastructure projects face huge challenges.
Each project has a relevance and a unique nature, although, they are developed in conditions
and environments more or less similar. This paper describes different progress that were
accomplished in drafting, integrating and evaluating various projects focussed to specify,
design, build and commissioning industrial irradiation plants based on electron beam in
Mexican territory.
Having as a background the experience that ININ has gained since 1980, when its Gamma
Industrial Irradiation plant was commissioned and 1983, when its commercial operation
started, the key elements to consider related to the installation of new irradiation plants
based on electron beam are:
1. The market demand that justifies the need to have the facility.
2. Other additional key drivers that strength the arguments to install a new facility.
3. The different kinds of regulations, the legal framework, types of technologies and the
particular requirements of industries wherein the supply of irradiation services will
be focussed like medical disposables and food products.
4. The technical details to fulfil the specification of irradiation service that the facility
will offer to the customers: desired effects onmaterials, uniformity and range of doses,
guarantee, quality control and complementary services like microbiological analysis
or dose mapping, risk management among users and services by the supplier.
As a result given considerations, it may be possible to have a solid foundation to draft,
integrate and evaluate a new project. The next step should be the cost-benefit analysis
taking into account aspects related with market study, the legal framework and a sensitivity
analysis. Costs of the project should be treated with the sufficient detail according with the
level of development of the Project.
Fromwhat was mentioned above, any organization has the possibility to define the technical
characteristics of the main equipment, basically, the EB accelerator required: energy, EB or
EB and X-rays, power, type of technology (Linac, RF), among others.
The experience shows that if at the very beginning exists uncertainty about the financial
resources for the project, it is very convenient to have alternatives available since the very
early stages to face changes on the scope and on the specific requirements of diverse budget
sources, these issues could assure the success of the project.
IAEA–CN–241–273 179
A14
ICARST–2017
A15: Emerging Radiation Technologies
180
A15
Ramamoorthy Talk: Session A15, Friday 11:15 A15-01
Economics of Radiation Processing Technology: Posers and
Prospects
N. Ramamoorthy1,2
1Retiree from International Atomic Energy Agency (IAEA), Vienna, Austria
2Bhabha Atomic Research Centre (BARC), Mumbai, India
Corresponding Author: N. Ramamoorthy, nramasta@gmail.com
Radiation processing of materials for a variety of applications has been well-established,
and is also continuing to evolve further. The cost of radiation treatment, that is, say, dollar
per kGy per kg, is dependent on several factors of the radiation facility and operations, and
almost always irrespective of the nature of material being treated. Consequently, materials
of higher value like medical disposables, most spices, etc., have been more favourable for
radiation treatment from the point of view of economics. Furthermore, certain minimum
overhead cost is invariably present in all cases, and thus low-dose requirement for certain
commodity may not necessarily mean lower cost for radiation treatment. The absorbed
radiation dose required is known to vary (Gy to kGy) over a few orders of magnitude,
and for a single radiation facility to cater to the entire range is a known challenge. There
are technology options but they come with added complexities. The scope for year-round
availability of the same material, or a group of materials, requiring radiation processing
is another key issue to be addressed. Yet another dimension of technology has been the
availability of a choice between γ-radiation plant and electron accelerator (EB machine)
facility, each with its own strengths and issues. The ease and ruggedness of operation of
60Co based plants and their modest infrastructural needs are appreciable and proven records
are available. However, the availability and transportation of sources for replenishment,
and mostly fixed-dose delivery feature of the γ-facility pose certain limitations. EB systems,
especially of variable energy and power, would prove advantageous, while the ease and
ruggedness of their routine functioning over sustained, long-periods has very limited record,
leave alone the need for assured availability of high-quality power supply (issue in many
countries). Mostly two major areas of use are contemplated by the stakeholders, namely,
sterilization or hygienization of products on one hand, and tackling and treating pollutants,
on the other hand. Safe and often prolonged preservation is the need in the former case
and for cost consideration. The risk and cost to society and environment by not-treating the
harmful pollutants in managing them are the drivers in the latter case. Placing a simple
dollar figure here may not be necessarily feasible or easy. Naturally, for policy makers and
end-user stakeholders, the above scenario presents an equivocal picture, of an attractive
technology available for value-addition, but with techno-economic challenges. The author
has had experience in dealing with stakeholder experts from IAEA Member States, and
earlier in India with different industries seeking to use radiation processing. Invariably,
objective, frank analysis of every specific case has been necessary and useful to better
understand and/or explain the various aspects and factors to be addressed. It is imperative
for technology experts to speak in single unequivocal language to the national policy makers
and end-user stakeholders, so that the considerable merits of radiation processing are well
harnessed to meet every specific national need and priority.
IAEA–CN–241–059 181
A15
A15-02 Talk: Session A15, Friday 11:35 Wach
Radiation Modification of Carboxymethylated Chitosan: From
Basics to Applications
R. Wach1, P. Ulański1, and J. Rosiak1
1Lodz University of Technology, Łódź, Poland
Corresponding Author: R. Wach, wach@mitr.p.lodz.pl
The mainstream of radiation modifications of polysaccharides was limited to reduction of
molecular weight due to main-chain degradation in order to facilitate further processing or
induce specific biological activities. On the other hand, graft polymerization of functional
monomers initiated through radicals crated by ionizing radiation on polysaccharide chains,
or as effect of glycosidic bonds cleavage, was also extensively explored. The possibility
of cross-linking of polysaccharides by radiation initiation was demonstrated, firstly for
water-soluble cellulose derivatives, yet high degree of substitution (DS) of cellulose with
side chains and high concentration in aqueous solution were found to be advantageous
to obtain significant yield of gel fraction. In the present investigation, the behaviour of
carboxymethylchitosan under ionizing radiation was explored and exemplary application
proposed.
Carboxymethylchitosan (CMCS) of the deacetylation degree (DDA) 93.8%, DS 96% was
obtained from Kraeber & Co., GmbH (Germany). Medical grade chitosan (CS) obtained
from Heppe Medical Chitosan GmbH (Germany), with DS 90% was also used. Solutions of
CMCS and CS were irradiated by electron beam (EB) with and without a cross-linking agent
of poly(ethylene glycol) diacrylate (PEGDA, Sigma-Aldrich). Obtained gels were evaluated
by standard sol-gel analysis.
Results of this study indicated that ionizing radiation is a convenient tool to synthesize
hydrogels based on CMCS either with or without PEGDA when irradiated in highly con-
centrated solutions, whereas CS, its parent polysaccharide, as expected, is prone to form
gels only in the presence of the cross-linking agent. The method engaging PEGDA allows
formation of macroscopic gels even from a CMCS and CS solutions of low concentration
resulting in gels of gel fraction as high as 80%, which is distinct from the known technique of
polysaccharide cross-linking in the paste-like state: irradiation of CMCS 20% concentration
results in gel fraction less than 50%. The CMCS gels were found not to cause cytotoxic-
ity (as tested by LDH assay) and demonstrated antimicrobial activity, especially towards
gram-negative bacteria.
If the dose applied for gel formation is 25 kGy or more, it may be sterilized simultaneously
during its synthesis. This was explored (CMCS aqueous solution) in manufacturing of
internal hydrogel scaffold for nerve regeneration guides. Regular nerve guidance tubes of
polylactide and polycarbonate, elaborated in our laboratory, were filled with CMCS mixture
with water (paste like-state or physical gel, based on conditions determined in this study)
and irradiated with EB. After in situ synthesis of the gel inside the tube, the product is ready
for immediate use, because applied technology combines gel formation and sterilization
into a single process.
182 IAEA–CN–241–415
A15
Lassalle Talk: Session A15, Friday 11:45 A15-03
Remediation of Petroleum Impacted Soils with Electron Beam
Irradiation
J. Lassalle1, D. Staack1, T. Thompson1, M. Martinez1, H. Rao Damarla1, P. Bireta2,
G. Sabadell2, T. Hoelen2, and A. Strzelec1
1Texas A&M University, College Station, TX 77840, USA
2Chevron Energy Technology Company, San Ramon, CA 94583, USA
Corresponding Author: J. Lassalle, jdl1127@tamu.edu
Pollution of soil by heavy hydrocarbons (HH, C12–C40) is a major global environmental
issue. Heavy hydrocarbons pose a significant remediation challenge because they are
recalcitrant and relatively immobile in soils, and hence will persist in the environment for a
long time. Electron beam has the potential to both crack and polymerize hydrocarbons at
lower temperatures than similar energetic methods for HH remediation such as thermal
desorption and pyrolysis. Electron beam remediation must be proven fast, efficient, and
economical at large scales. To this end, the present research has several objectives: show
reduction in mass of heavy hydrocarbons in soil for proof of concept; assess impact of
testing parameters (such as radiation dose); and design an experimental setup to evaluate
soil treatment, both in a batch configuration and in a continuous configuration.
Samples with initial HH contamination ranging from 2% to 10% (w/w) were irradiated with
an 18 kW, 10 MeV RF LINAC in various configurations. Configurations including stationary
and moving soil containers were developed to irradiate samples ranging in size from 100 g
to 3 kg. Various doses were tested from 50 kGy to 2000 kGy to assess the energy cost and
effectiveness of various levels of remediation. Beam penetration profiles and HH reduction
profiles in the soils were measured. Similar soil samples were also thermally desorbed
and pyrolyzed to compare energy input to irradiation at similar maximum temperature
(„ 420˝C) and to characterize chemical reduction mechanisms during irradiation. Treated
and untreated samples were characterized using colourimetry and gas chromatography
(GC-FID) performed with hydrocarbon solutions in dichloromethane.
Tests showed effective HH mass reduction, which resulted in TPH reduction (below 0.1%,
satisfying environmental regulations) in both batch and continuous treatments. Temperature
programmed desorption and oxidation (TPD/TPO) showed evidence of both volatilization
and char formation as the means of heavy hydrocarbon mass reduction.
IAEA–CN–241–220 Presenter: D. Staack 183
A15
A15-04 Talk: Session A15, Friday 11:55 Driscoll
Electron Beam Pretreatment of Lignocellulosic Biomass
M. Driscoll1, A. Stipanovic1
1College of Environmental Science and Forestry, State University of New York (SUNY),
Syracuse, NY 13210, USA
Corresponding Author: M. Driscoll, mdriscol@esf.edu
Cellulose is the major structural component of wood and plant fibres and is the most
abundant polymer synthesized by nature. Despite this great abundance, cellulosic biomass
has seen limited application outside of the paper industry. Its use as a feedstock for fuels
and chemicals has been limited because of its highly crystalline structure, inaccessible
morphology and limited solubility. Any economic use of lignocellulosic resources for the
production of fuels will require a “pretreatment” technology to enhance the accessibility of
the biomass to enzymes and/or chemical reagents. Most pretreatment techniques either are
energy intensive or require the use of toxic chemicals. In this study electron beam irradiation
was used as a pretreatment technique.
Samples were irradiated at IBA Industrial, Edgewood, New York, USA, using a 90 kW, 3 MeV
Dynamitron. Most samples were less than 0.5 cm thick with a bulk density of ă 0.6 g/cm3,
thus giving equal-in equal-out dose. Thick (2.5 cm) wood boards were irradiated from both
sides giving a uniform dose profile. The dose was determined with cellulose triacetate films.
Molecular weight was determined using a Waters Breeze size exclusion chromatography
system fitted with a Waters 2414 refractive index detector, and two Polymer Laboratories
Polypore columns (330ˆ7.5 mm2). The relative crystallinity was determined using a Rigaku
DMAX-1000 X-ray diffractometer with Ni-filtered Cu Kα radiation (λ “ 0.15418 nm). All
other tests were conducted in accordance with ASTM or TAPPI standards and gravimetric
analysis.
As the dosewas increased from 0 to 1000 kGy, themolecularweight decreased from 80 000 to
5000 Da and the relative crystallinity decreased from 0.87 to 0.45. The wood toughness and
energy required for milling was decreased by about an order of magnitude. The solubility
of irradiated wood in water, 0.2 N NaOH and 2.0 N NaOH increased with increasing dose
with 95% of the wood soluble in 2.0 NNaOH after 1000 kGy. The hot water extraction of
hemicellulose and lignin increased along with dose. The extracted lignin also showed an
increase in solubility in acidic solutions. Most importantly, the rate and total sugar yields
from enzymatic hydrolysis increased with increasing dose. There did not appear to be any
“poisoning” of fermentation to ethanol due to the presence of furfurals. Sugars extracted
from irradiated wood shows an increase in the rate of fermentation.
Electron beam irradiation of lignocellulosic biomass appears to be an excellent pretreatment
technique to reduce the recalcitrance of the biomass. Electron beam treatment is less
energy intensive and does not use or produce toxic chemicals than other pretreatment
techniques. Electron beam treatment reduces the crystallinity and molecular weight of
cellulose, increases hot water extraction of lignin and hemicellulose, and increases the rate
and total sugar produced by enzymatic hydrolysis.
184 IAEA–CN–241–373
A15
Hemvichian Talk: Session A15, Friday 12:05 A15-05
Radiation-Induced Admicellar Polymerization of Methyl
Methacrylate on Cassava Starch
K. Hemvichian1, P. Suwanmala1, W. Kangsumrith2, and T. Pongprayoon3
1Thailand Institute of Nuclear Technology, Bangkok, Thailand
2Thammasat University, Pathum Thani, Thailand
3King Mongkut’s University of Technology, Bangkok, Thailand
Corresponding Author: K. Hemvichian, kasineeh@yahoo.com
Cassava starch (CS) is a natural polymer that is inexpensive and abundant, especially in Thai-
land. In addition to being cost-effective, CS is also biodegradable, compostable, non-toxic
and most importantly, renewable. Consequently, blending CS with other biodegradable
synthetic polyester such as poly(lactic acid) (PLA) is economically interesting, due to a high
potential of cost reduction as well as biodegradability of their blends. Nevertheless, it is very
difficult to blend starch with other synthetic polymers, due to their incompatibility. Several
research groups reported their attempt to improve the compatibility between synthetic
polymers and starch using different techniques. Among these available methods, the modi-
fication of starch surface by admicellar polymerization is rarely investigated. Admicellar
polymerization offers several advantages over traditional techniques. Accomplished in aque-
ous solution, this environmentally friendly technique can form nanoscale polymeric thin
films, with minimum chemical usage and without the use of organic solvents. Additionally,
this benign technique is able tomaintain basic properties of the original material. Admicellar
polymerization is applied to induce surface modification to make two components of their
polymeric composites more compatible. Applications of admicellar polymerization are
numerous, from reinforcements of composites to value addition of functional textiles. These
examples emphasize the advantages of using admicellar polymerization as an effective
method to enhance compatibility between a filler and a polymer matrix, which ultimately
leads to improved mechanical properties of their composites. Our recent work has proven
that admicellar polymerization, induced by thermal process, can be successfully applied
to coat the surface of starch with poly(methyl methacrylate) (PMMA) to render it more
hydrophobic and more compatible with PLA. The objective of this research is to further
expand our previous study by applying γ-radiation to induce admicellar polymerization.
The third step of admicellar polymerization is traditionally induced by thermal process,
with chemical initiators. However, radiation process requires no catalyst to initiate the
reaction, thus resulting in contamination-free products. In this study, methyl methacrylate
(MMA) is used as a monomer for the formation of ultra-thin PMMA film on the surface
of CS. Surface modified CS is characterized by iodine test, flotation test, film formation
analysis, Fourier transform infrared spectroscopy (FTIR) as well as thermal gravimetric
analysis (TGA). The comparison is made between cassava starch modified by radiation
process (RS) and thermal process (TS). Results from film formation analysis, FTIR and
TGA indicate that RS shows higher percentage of PMMA film formation than TS, hence
confirming that radiation processing can be applied as an alternative method for surface
modification through admicellar polymerization.
IAEA–CN–241–227 185
A15
A15-06 Talk: Session A15, Friday 12:15 Doan
Preparation and Characteristics of Reduced Graphene Oxide in
Ethanol/Water Solution by γ-Ray Irradiation
B. Doan1, T. D. Nguyen1
1Research and Development Center for Radiation Technology (Vinagamma), Ho Chi Minh City, Viet Nam
Corresponding Author: B. Doan, doanbinh192@yahoo.com
Reduction of graphene oxide (GO) in ethanol/water solution in the presence of oxygen by γ-
ray irradiation was studied. Suspension of GOwas prepared by dispersing graphite oxide in
the ethanol/water solution at a concentration of about 1 mg/m` under ultrasonic condition,
and then irradiated by γ-rays in an absorbed dose range of 0–250 kGy. The characteristic
properties of GO and reduced GO (RGO) samples were analyzed by Ultra-violet visible
(UV-Vis) spectroscopy, Fourier-transform infrared spectroscopy (FTIR), X-ray diffraction
(XRD), Raman spectroscopy, Transmission electron microscopy (TEM), contact angle and
electrical conductivity measurements. The conductivity of the RGO was increased from
2.4 ˆ 10´2 to 2.2 S/cm with increasing the absorbed doses from 25 to 250 kGy. Results
of this study were indicated that a promising way could produce a large amount of pure
graphene from GO with a simple reducing process using the γ-irradiation method.
186 IAEA–CN–241–384
A15
Wu Talk: Session A15, Friday 12:25 A15-07
Radiation Induced Oxidation, Cross-Linking and Grafting of
Ultra-High Molecular Weight Polythylene
G. Wu1, H. Wang1, and L. Xu1
1Shanghai Institute of Applied Physics (SINAP),
Chinese Academy of Sciences, Shanghai, People’s Republic of China
Corresponding Author: G. Wu, wuguozhong@sinap.ac.cn
Ultra-high molecular weight polyethylene (UHMWPE) has excellent chemical inertness,
biocompatibility, mechanical property and wear-resistance, which is widely used in engi-
neering and medical fields. Some drawbacks of UHMWPE can be overcome by radiation
processing, such as poor compatibility, creep-resistance and yield strength. In this work,
radiation oxidation and grafting were adopted to modify the surface property of UHMWPE.
Radiation cross-linking and annealing were used to improve the creep-resistance, yield
strength and wear resistance of UHMWPE. The results indicated that radiation oxidation
and grafting could effectively change chemical groups on the surface of UHMWPE. How-
ever, radiation oxidation could not remarkably improve the surface property of UHMWPE,
such as hydrophilicity, even at a dose of 300 kGy by γ-irradiation in air. Radiation grafting
of acrylic acid could significantly improve the hydrophilicity of the UHMWPE powder. The
UHMWPE powder with grafting yield of less than 10% presented a good dispersion in
water. Radiation cross-linking and annealing improved creep-resistance and yield strength
of the UHMWPE sheets. The cross-linked UHMWPE sheet with a dose of 300 kGy was
without obvious deformation under a load of 0.06 MPa at 270˝C in 4 h. In addition, the
cross-linked UHMWPE powder as an additive, even at low content, could improve the wear
resistance of pristine UHMWPE. In conclusion, the surface and mechanical properties of
UHMWPE can be effectively improved by radiation processing.
IAEA–CN–241–403 187
A15
ICARST–2017
B01:Advances and Trends in Radiotracer and
Radiation Science and Technology I
188
B01
Nguyen Huu Talk: Session B01, Monday 11:15 B01-01
Improved Procedures for Preparation of Argon-41 Gaseous
Radiotracer from Solid Clathrate Compound
Q. Nguyen Huu1, H. Tran Tri1, N. Huynh Thai Kim1, and T. D. Dang Nguyen1
1Centre for Applications of Nuclear Technique in Industry (CANTI), Dalat City, Lamdong Province, Viet Nam
Corresponding Author: Q. Nguyen Huu, nhquang.dalat@gmail.com
Argon-41 can be a very good gaseous radiotracer for industrial applications if a sufficient
amount of activity is produced from the reactor. The common procedures for preparing
Argon-41 by irradiation of a quartz ampoule containing compressed argon gas give such
low efficiency that the produced activity is not sufficient to compensate the 41Ar decay
during transportation to the field.
This paper introduces procedures for preparing argon in a solid clathrate compound with
hydroquinol in which the concentration of argon reaches 7% by weight. The stability of
the argon clathrate allows production 41Ar in the reactor safely at the sufficient amount. In
the field, radioactive argon gas is liberated from hydroquinol crystals by dissolving with
water or alcohol solvent. The experiments tracing gas flow using 41Ar and methyl-82Br as
reference tracer were carried out to test the procedures.
The procedures have improved the efficiency of 41Ar gaseous tracer production to the level
of GBq activity for industrial application.
IAEA–CN–241–039 189
B01
B01-02 Talk: Session B01, Monday 11:35 Kalo
Experimental Study of Conical Fluidized Bed Using
Radioisotope Based Technique
L. Kalo1, H. J. Pant2, and R. K. Upadhyay1
1Indian Institute of Technology, Guwahati, India
2Bhabha Atomic Research Centre (BARC), Mumbai, India
Corresponding Author: L. Kalo, k.lipika@iitg.ac.in
Gas-solid conical fluidized beds are used for several applications like drying, food process-
ing, granulation, combustion, gasification, coating of nuclear fuel particles, crystallization,
catalytic cracking, sulfide ores sedimentation and particle classification, etc. The design pa-
rameter for such applications depends completely on the bed behaviour. However, research
on conical fluidized beds shows that literature at in situ condition is currently lacking. So
the investigation of conical gas-solid fluidized beds for in-situ conditions is required for the
basic understanding of the flow pattern and bed behaviour which can be implemented for
better design and process scaling of the column.
The radioisotope based technique known as radioactive particle tracking (RPT) technique
and densitometry have been applied for the study of conical fluidized bed. In the RPT
technique, one radioactive particle (glass bead in this case) is doped with scandium-46. This
tracer particle is used as marker whose motion is tracked by using 10 NaI(Tl) scintillation
detectors. The position of the tracer particle is reconstructed by using the count time series
map recorded by each detector. Further post-processing, like particle position time series
data, Lagrangian velocity time series, mean and rms velocities of the particle, is calculated
by using the count time series map. In addition, the densitometry technique is used to
measure the chordal average solid volume fraction at different axial and radial locations of
the bed.
The conical column used comprises of 0.8 m conical section height and 0.05 m diameter
at bottom increasing along height until 0.2 m on top. Two different particles (diameters
0.6 mm and 1 mm) having density 2500 kg{m3 are used. Both mono-dispersed and binary
bed behaviour is studied to characterize the mixing and segregation. The bed composition
has been varied as 0 : 100, 25 : 75, 50 : 50, 75 : 25 and 100 : 0 to visualize the effect of
composition with velocity. The total bed weight is kept constant for all experiments. In
binary fluidized bed both the particle are tracked individually. Both RPT and densitometry
have been conducted for three different velocities (2 umf , 3 umf and 4 umf of 1 mm particle).
Results indicate that the solid volume fraction becomes uniform with increase in velocity,
signifying better mixing with velocity increase.
Mixing and segregation studies are performed in mono-dispersed and binary fluidized bed.
It is observed that the volume fraction of solid particles shows uniform distribution with
increasing velocity.
190 IAEA–CN–241–241
B01
Phirani Talk: Session B01, Monday 11:55 B01-03
Predicting Dead Pore-Volume of Pores in a Porous Media from
Single Tracer Experiment
J. Phirani1, H. J. Pant2
1Indian Institute of Technology, Delhi, India
2Bhabha Atomic Research Centre (BARC), Mumbai, India
Corresponding Author: J. Phirani, jyotiphirani@gmail.com
Tracer studies are used to characterize the porous media for flow paths of different phases,
pore volume and flow surface area in reactors or oil reservoirs. The stagnant or dead pore
volume interacts with the tracer leading to a tailing effect in the tracer breakthrough curve.
Therefore, the effluent concentration profile from a single tracer test is not sufficient to char-
acterize the porous medium. Generally, numerical simulation of the effluent concentration
profile with parameter fitting is used to determine and separate the effect of dead pore
volume from other tracer behaviour in the porous medium such as dispersion or adsorption.
In laboratory experiments, the tracer test is done at various flow conditions to determine
the effect of dead pore volume. Numerical simulation of huge reactors and reservoirs is
computationally expensive and the imposition of different flow conditions is difficult at
industrial scale. The goal of this work is to develop a model for the determination of dead
pore volume from a single tracer experiment for homogeneous, one-dimensional flow in
porous media.
The effluent concentration profiles of the tracer from numerical experiments of tracer trans-
port in porous media are used to arrive at the model to determine the dead pore volume
and the surface area associated. Mechanistic models of tracer transport in porous media are
used in the simulations.
The pore volumes injected, flow rate, axial dispersion and tracer diffusivity in the dead
pore volume are found to be the governing parameters for determining the fraction of
dead pore volume in the porous media using single tracer test. Conventionally, numerical
simulations with parameter fitting to match the effluent tracer concentration have been used
to characterize the porous medium for effective porosity and mobile porosity by modelling
the tracer’s flow and chemical behaviour in the sediments. The model developed here can be
directly used to infer the reservoir parameters of mobile porosity from the tracer’s effluent
concentration profile from single tracer experiment.
IAEA–CN–241–232 191
B01
B01-04 Talk: Session B01, Monday 12:15 Roy
Application of RPT and Densitometry for Measuring Liquid
Velocity Field and Void Fraction in Convective Boiling Flows
S. Roy1, H. J. Pant2, and A. Yadav1
1Indian Institute of Technology, Delhi, India
2Bhabha Atomic Research Centre (BARC), Mumbai, India
Corresponding Author: S. Roy, roys4095@gmail.com
Convective boiling flows are found in nuclear reactors and are subject of numerous experi-
mental and theoretical studies. The thermal hydraulics of the nuclear reactor, especially
boiling water reactors (BWR), is affected by the complexities of two-phase flow around the
rods driven by a vertically distributed heat flux in the rods. One of the main challenges in
operating this kind of a reactor system are in the complexities of two-phase flow around the
rods driven by a vertically distributed heat flux in the rods. Knowledge of the time-averaged
void fraction distribution as well as the velocity profiles of the liquid phase are of great
relevance in the design of these systems, for providing validation data for thermal-hydraulic
CFD codes, as well as for design of nuclear safety systems.
In this contribution, measurement of the liquid phase velocity field and void fraction using
RPT and densitometry, respectively, at different conditions and heater rods arrangements
will be reported.
The talk will discuss the various challenges faced in making these measurements in boiling
flows, and how they were overcome. Further, key findings from the hydrodynamics, which
can be obtained only through the use of these radiation-based imaging techniques, will be
presented.
192 IAEA–CN–241–410
B01
de Mesquita Talk: Session B01, Monday 12:35 B01-05
Holdup Analysis of a Bubble Column Using an Industrial
Fourth Generation Like γ-Ray Tomography
C. H. de Mesquita1, A. Velo1, D. V. Sousa Carvalho1, L. D. J. Ribeiro1, and M. Hamada1
1Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), São Paulo, Brazil
Corresponding Author: C. H. de Mesquita, chmesqui@usp.br
This work has been performed using the fourth-generation-like industrial computed tomog-
raphy developed at the IPEN, constituted with 70 NaI(Tl) 25.4 mmˆ 50.8 mm (diameter ˆ
length) and a bubble column for industrial process was evaluated. The column is a Perspex
glass cylindrical tube of 80 mm internal diameter, 100 mm external diameter and 1400 mm
height constituted the following parts: liquid circuit (water), a gas circuit (4 `{min) bubbled
into a system containing two limiting holes of 4 mm and 2 mm, located at 65 mm from the
centre of the column each one in opposite side. γ-ray tomography experiments were carried
out, using this simulator column both empty and filled with water plus gas bubbling. In this
work the scanner was set for 5 views and 14 projections each. The resulting images describe
the liquid or gas phase holdup distributions for bubbles generated in a hole of 4 mm and
2 mm diameters located at 15 mm of the column wall in a opposite side, respectively. It
was established that the newly developed fourth-generation-like fan-beam arrangement
γ-scanner unit has a good temporal resolution acceptable given the size of the column used
in this study and capable to infer the relative proportional of gas and liquid proportion in
the column.
IAEA–CN–241–399 193
B01
ICARST–2017
B02: Education, Training and Safety
194
B02
Potier Talk: Session B02, Monday 14:15 B02-01
A New Approach to Teach Beginners How to Analyze Tracing
Results by a Rapid Visual Method
O. Potier1
1Université de Lorraine, CNRS, Nancy, France
Corresponding Author: O. Potier, olivier.potier@univ-lorraine.fr
When people learn how to analyze the results of residence time distribution (RTD) experi-
ments, it is very difficult for them to immediately be able to form pertinent ideas concerning
the kind of mixing only by looking at the RTD curve; the difficulty remaining in the un-
derstanding of the effects of flows in the system (in parallel and/or series, recirculation,
etc.) on the global RTD curve. Everyone needs significant experience to be able to do that
(from several months up to years). However, this period can be significantly reduced. To do
this, we developed a new visual method to teach RTD analysis complementing the classical
method (theory of residence time, transfer functions, simple systems like CSTR or plug
flow reactor). We use the software DTS®. The students use it in an unusual way, to do
simulations of reactors associations from the simplest to the very complex. We tested the
method over several years with students preparing a master of engineering degree, and we
progressively improved the different reactor configurations, to optimize teaching efficiency.
Now, in only one or two hours, students testing a dozen selected configurations can gain
the equivalent of several months of experience.
IAEA–CN–241–328 195
B02
B02-02 Talk: Session B02, Monday 14:35 Livolsi
Education Training: INSTN Designated as an IAEA
Collaborating Centre
P. Livolsi1
1Commissariat à l’énergie atomique (CEA), Institut national des sciences et techniques nucléaires (INSTN),
France
Corresponding Author: P. Livolsi, paul.livolsi@cea.fr
The National Institute for Nuclear Science and Technology (INSTN) created in 1956 by the
French government has been designated as an IAEA Collaborating Centre in May 2016.
This recognition allows the Agency to receive support from this Institute to implement its
programmes including those from the Department of Nuclear Sciences and Applications.
The competency of this collaborating centre is “Education and Training in nuclear tech-
nologies industrial and radiopharmaceutical applications”. The INSTN and the Agency
have defined a work plan to host specific training courses, and to develop new training
courses in connection with INSTN’s areas of expertise. Thus at the end of June 2017, a
three weeks training course on “Training and Certification for Industrial Applications of
Radiation Technologies: Radiotracers Residence Time Distribution Approach and Sealed
Sources Column Scanning Technique” will be organized in Saclay, near Paris. Through
column scanning equipment dedicated to training, innovative training methods, practical
room for manipulating radiotracer, theoretical contributions will be delivered by experts
from the Agency and practical work will be carried out by participants consisting of both
fellows of the Agency but also professionals from the host country. This training will benefit
from the infrastructure and logistics of the INSTN for the safe use of radionuclides used for
tracing.
The INSTN as a part of the French Atomic Energy Commission (CEA), is under the joint
supervision of three ministries: Ministry of National Education, Higher Education and
Research, Ministry of the Economy, Industry and the Digital Sector, and Ministry of Ecol-
ogy, Sustainable Development and Energy. The Institute has partnerships with various
universities and higher education institutions in France and abroad but also with technical
schools for academic degree from operator to PhD diploma, mostly in the nuclear domain.
The Institute organizes tailor-made professional training courses in France or abroad and
support continuing professional development so as to increase staff skills in a large spectrum
of nuclear activities such as: nuclear engineering and applications, detection and measure-
ment of radiations; radiation protection, chemistry and radiochemistry; Nuclear medicine,
radiopharmacy, medical physics, radiotherapy and molecular imaging; new technologies
for energy, economics of energies; micro and nanotechnologies.
In the field of academic and vocational training, INSTN signed an additional agreement
with the IAEA in 2014 which helped to launch the Virtual Reactor Laboratory (Internet
Reactor Laboratory) project, which will allow students from European universities a remote
access, via the Internet, to the ISIS research reactor (nominal power of 700 kW). These
students can monitor, through a video system (via Internet), the operation of the ISIS reactor
by exchanging with a trainer-operator present in the control room of the installation of the
CEA-Saclay. For 60 years, the INSTN is a key-player in France for education and training in
nuclear domains such as industry, research and medical. Being designated a Collaborating
Centre will strengthen connections that INSTN has with the IAEA.
196 IAEA–CN–241–433
B02
Brisset Talk: Session B02, Monday 14:55 B02-03
Training and Certification in Radiotracers and Sealed Sources
Industrial Applications
P. Brisset1, J. Thereska2, and H. Ben Abdelouahed3
1International Atomic Energy Agency (IAEA), Vienna, Austria
2Institute of Applied Nuclear Physics, University of Tirana, Tirana, Albania
3National Center for Nuclear Sciences and Technologies (CNSTN), Sidi Thabet, Tunisia
Corresponding Author: P. Brisset, p.brisset@iaea.org
The International Society of Tracers and Radiation Applications (ISTRA) has been created
in 2015 with its HQ in Vienna as the federation of Tracers and Radiation Application teams
in the world with about 500 members today.
IAEA activities regarding capacity building are mainly conducted within TC projects
through fellowships, scientific visits and expert missions. It has been clearly seen that
there is a lack of structure in these trainings. FE hosts, RTC organizer experts are doing their
best providing good work but they do what and how they wish, think and can. It is also
quite difficult to synchronize the event with real field work to allow practical experience for
the trainees.
We have to fix these issues and for that, in collaboration with IAEA, ISTRA has developed
syllabuses, e-learning modules and question banks on radiotracers applications (RTD ap-
proach, TCS 31, 38 and 49), sealed sources applications (column scanning, NBS-TCS in
publication process), tracers and NCS applications in sediment transport (TCS 59).
The global objective is to create a training and certification system for practitioners, with
ISTRA acting as the examination and certification body worldwide.
The system has three levels of qualification, similar to the NDT system, based on the
recognized syllabuses and examination:
• Level 1: helper/assistant
• Level 2: autonomous practitioner
• Level 3: team leader
Beside the better structure of the courses and the associated examination, it is also helping
the practitioners and teams in promotion of the technologies, by improving the visibility
and recognition of the qualification of personnel.
Today approximately 50 practitioners have been trained, qualified and certified in Africa
and Latin America and the Caribbean regions. Unfortunately, due to the lack of TC projects,
nobody in Europe or the Asia-Pacific regions has yet profited.
IAEA–CN–241–454 197
B02
B02-04 Talk: Session B02, Monday 15:15 Telleria
The IAEAMethodology for Radiological Protection of the
Environment, Including Human and Non-Human Biota
D. Telleria1
1International Atomic Energy Agency (IAEA), Vienna, Austria
Corresponding Author: D. Telleria, d.m.telleria@iaea.org
In 2005 the IAEA started to work with international organizations and Member States
towards enhancing international standards and guidance for the control of radiological
impacts to people and the environment. Until then, protection of the environment was based
on the assumption that compliance with standards for human protection would ensure that
other species are not put at risk; this assumption was being challenged by the international
community. IAEA standards considering a new perspective were started in 2006 with the
Fundamental Safety Principles and continued with the IAEA Basic Safety Standards on
Radiation Protection and the Safety of Radiation Sources. In these standards, the radiation
protection objectives for non-human species were related to higher organization levels as
populations, communities and ecosystems, rather than on the protection of individuals as it
is the case for humans; the need to consider protection of humans and other species in an
integrated manner was also recognized. The IAEA followed the 2007 recommendations of
the ICRP on protection of the environment, and proposed an assessment methodology for
flora and fauna similar to that applied for demonstrating compliance of doses to humans
with predefined criteria. The method entails the use of a set of reference animals and
plants (RAPs) that relates to various species and ecosystems. Radiation exposure levels
can be estimated and compared to identified criteria below which no or only very limited
adverse effects to biota are expected. The integration of the protection of humans and
other species was approached by assuming the linkage of the exposure scenarios between
humans and flora and fauna. This resulted in a practical methodology which can be
implemented with basically the same resources as those used to demonstrate protection
of humans; the effectiveness of the approach to protect flora and fauna is verifiable by
environmental monitoring programmes similar to those already in place for the humans
exposures pathways, considering the relevant media. The IAEA established different ways
to consider protection of biota for different exposure situations. For planned exposure
situations, the results of the estimation of exposures to RAPs are compared to reference
levels, and this could imply the need of control of the source. For existing and emergency
situations, the control of those exposures is limited or impossible and the results of the
assessments should be considered as an aspect in the optimization process, together with
others, like social and economic factors. The paper presents the methodology developed by
the IAEA and its implementation in international legal instruments, like in the Convention
on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter and the
OSPAR Convention for the Protection of the Marine Environment of the North-East Atlantic,
and in recently prepared IAEA Safety Guides.
198 IAEA–CN–241–451
B02
Mahjoub Talk: Session B02, Monday 15:35 B02-05
Radiation Sciences and Applications Programme in Arab
Countries
A. Mahjoub1, S. Takriti1
1Arab Atomic Energy Agency, Tunis, Tunisia
Corresponding Author: A. Mahjoub, am.mahjoub@yahoo.fr
TheAAEAworks since 1989 to enhance the socio-economical development in Arab countries
by promoting the peaceful applications of atomic energy in many aspects of life.
The AAEA is implementing “The Arab Strategy for Peaceful use of Atomic Energy up to
2020”, which focusses on: the introduction of nuclear science in educational institutions;
the use of nuclear technologies to improve plant and animal production; food and radia-
tion processing methods; the use of nuclear technology in the diagnosis and treatment of
diseases; the use of nuclear techniques in water resources management; the integration of
the production of radioactive isotopes among Arab countries; the use of EB accelerators
in irradiation operations and processing materials; the use of ion accelerators in the field
of analysis and properties improvement and strengthening and promoting of the Arab
capabilities in the field of NDT.
Under the framework of the above topics, AAEA has implemented many training courses,
workshops, experts meetings, expert missions, scientific visits, conferences and seminars
which will be detailed in the presentation.
For the implementation of the activities, AAEA is using country infrastructure such as: re-
search reactors (RRs) that can produce radioisotopes (Egypt–2, Algeria–2, Libya–1, Morocco–
1, Syria–1, Jordan–1); ion accelerator (cyclotron) for the production of radioisotopes such as
PET (Morocco, Algeria, Syria, Saudi Arabia, Egypt); ion accelerator (VDG) for material re-
searches and analysis (Egypt, Syria, Jordan, Lebanon, Algeria); electron accelerator (LINAC)
for research and industrial applications (Tunis, Egypt, Syria, Morocco, Saudi Arabia, Algeria,
UAE, Kuwait); electron accelerator (LINAC) for nuclear medicine radiotherapy (all Arab
countries) and γ-irradiators (γ-ray) for medical applications and others (all Arab countries).
IAEA–CN–241–339 199
B02
B02-06 Talk: Session B02, Monday 15:55 Masinza
Quality Management in Radiotracer Technology and Sealed
Source Applications
S. A. Masinza1
1Kenya Accreditation Service (KENAS), Nairobi, Kenya
Corresponding Author: S. A. Masinza, masinzas@gmail.com
Radiotracer and sealed source applications technology for industrial processes have become
important non-destructive and noninvasive tools for on-line diagnosis of process malfunc-
tioning, optimization and predictive maintenance. The technologies have been developed
and established in many countries and are used by others as a routine service activity for
preventive maintenance of process columns and tanks in their local industries. The demand
for the technology has been found to be steadily increasing among the countries who have
developed local capacity and capability. Data interpretation from radiotracer and sealed
source applications are central in strengthening the development of the technology and
increasing its use in various industries.
The confidence by industry to use this technology (product) is enhanced if clients know
that it has been thoroughly evaluated by an independent, competent accreditation body
to provide the third party assurance that the inspection body is competent in all aspects
to apply it. Accreditation is a formal means of determining the technical competence of
inspection bodies to perform specific types of inspection. Accreditation provides a ready
means for customers to identify and select reliable inspection services, suitable for their
needs. Therefore, the need for inspection bodies applying the technology to establish quality
management systems and the means of achieving this is discussed in this paper. It also
provides a guide on how personnel certification by an accredited certification body can be
implemented.
200 IAEA–CN–241–424
B02
ICARST–2017
B03:Radiotracers for Industrial Processes
Optimization and Safety I
201
B03
B03-01 Talk: Session B03, Monday 16:30 Alami
Study by Radiotracer of a Phosphoric Acid Production Line
R. Alami1
1Centre National de l’Energie des Sciences et des Techniques Nucléaires (CNESTEN), Rabat, Morocco
Corresponding Author: R. Alami, rachad.alami@gmail.com
The principle of the study is based on the impulse-response concept. The pulse is obtained at
the studied reactor inlet by injection of the radiotracer. The study involved a phosphoric acid
production line, consisting in particular of two digesters (D1 and D2) and four crystallizers
(C1 to C4). Technically, the interest of the study is to establish the residence time distributions
to:
• Define mean residence times in the various reactors diagnosed;
• Define the arrival times, at all studied compartments: digesters D1 and D2, crystalliz-
ers C1 to C4;
• Identify the flow pattern in each reactor (perfect mixer, piston, etc.);
• Identify potential process failures (dead volumes, shorts, etc.).
The study was conducted in two phases:
• First injection of radiotracer, at the inlet of digester D1;
• Second injection of radiotracer, at the inlet of crystallizer C1.
The radiotracer used is 131I, as liquid Na131I.
The two injections of radiotracer have established with precision the residence time distribu-
tions in the studied reactors and flow regimes prevailing there. From the response-curves,
product arrival times and mean residence times were also determined.
202 IAEA–CN–241–360
B03
Yelgaonkar Talk: Session B03, Monday 16:45 B03-02
Studying Flow Dynamics of Catalyst Powder in CCU for
Troubleshooting
V. Yelgaonkar1, V. Dhakar1, P. Rao1, and B. K. Pathak1
1Board of Radiation & Isotope Technology, Department of Atomic Energy, Mumbai 400 001, India
Corresponding Author: V. Yelgaonkar, yelgaonkar@britatom.gov.in
γ-scanning and radiotracer applications are very effective and inexpensive tools to under-
stand and optimize the process as well as troubleshoot the various types of problems in
many chemical, petrochemical industries and refineries. These techniques are noninvasive,
hence the problems can be pinpointed online which reduces the downtime, helps schedule
the shutdown and maintenance of the plant equipment, thus rendering huge economic
benefits.
In a leading refinery of India, the catalytic cracking unit (CCU) was malfunctioning. It
was suspected by refinery engineers that the catalyst powder is being carried over to the
fractionator which could have lead to erosion of the fractionator column internals resulting
their rupture, consequentially creating a fire hazard. To understand the flow behaviour of
catalyst powder and to ensure the mechanical integrity, catalyst accumulation and choking,
both radiotracer study and γ-scanning of the CCU reactor was carried out. The reactor
consists of a riser, three primary cyclones and three secondary cyclones. γ-scanning of the
reactor was carried out with the help of automatic γ-scanner using 1.8 GBq of 60Co sealed
source. Results showed that catalyst powder was accumulated in one of the secondary
cyclones and uneven density distribution was observed in another secondary cyclone. The
radiotracer study was carried out using irradiated catalyst powder as a radiotracer which
contains 0.9 GBq of 24Na. The radiotracer was injected in the reactor through specially
fabricated injection system. Radiation measurement was done using thermally insulated
and collimated NaI(Tl) scintillation detectors located at various strategic locations coupled
to a multidetector data acquisition system. The data were mathematically analyzed. It was
confirmed that the catalyst powder was accumulated in one of the secondary cyclones with
no flow downwards. This resulted in excess powder available, to travel along with hydro-
carbon towards fractionator. Since the quantity of powder released through hydrocarbon
outlet of CCU was higher than the designed value, the catalyst powder was observed in
various zones of the fractionator. Mathematical modelling of the radiotracer data obtained
at various locations corroborated the scanning results.
IAEA–CN–241–031 203
B03
B03-03 Talk: Session B03, Monday 17:00 Affum
The Application of CFD for Modelling Flow and Visualization
in a Cement Mill and Experimental RTD Validation Using
Radiotracer Technology
H. A. Affum1, I. I. Mumuni1, C. P. K. Dagadu1, and S. Yamoah1
1Ghana Atomic Energy Commission (GAEC), Legon-Accra, Ghana
Corresponding Author: H. A. Affum, afmyn79@yahoo.com
Cement manufacturing represents an energy-intensive process due to the large power
consumption of mills which are an integral process units of the entire cement manufac-
turing process. Therefore, performance optimization of cement mills is key in ensuring
inefficiencies. Yet, performance optimization of such mills is impossible without adequate
technical information about the milling process. Experimental residence time distribution
(RTD) techniques are known to provide accurate process information and are useful in the
validation of computational fluid dynamic models of the particular process under study.
This first part of the study presents key process parameters of a cement mill obtained using
the radiotracer residence time distribution (RTD) technique at the Ghana Cement plant
located in Tema in the Greater Accra region of Ghana. Some 40 mCi of liquid 198AuCl4
agglomerated with cement powder and water was used as the radiotracer and introduced
at the mill inlet. The passage of the radiotracer at the outlet was monitored by an external
sodium iodide scintillation detector. Data analysis revealed the presence of dead zones or
channelling within the mill as indicated by the disparity in the experimental mean residence
time of 33.65 minutes and theoretical mean residence time of 58.15 minutes.
In the second part of the study, ANSYS CFD simulation software will be used to model the
flow in the cement mill for visualization as a complimentary method to the radiotracer RTD
technique. ANSYS DesignModeler will be used to create the geometry of the 11.4 m long
mill with a diameter of 3.6 m and ANSYS meshing used to create the computational mesh.
FLUENT, the fluid analysis tool of the ANSYS software, will be employed to calculate the
fluid flow throughout the geometry using the computational mesh, and CFD-Post for the
analysis of the results in the form of velocity profiles. Particle tracking discrete phase model
(DPM) will be used for the RTD simulation by tracking virtual particles injected at the inlet
of the mill and recording the time required for them to reach the outlet. The results of the
CFD simulation will aid the optimization of experimental parameters of the radiotracer
RTD technique for cement mill investigations.
204 IAEA–CN–241–132
B03
Ben Abdelouahed Talk: Session B03, Monday 17:15 B03-04
Radiotracers for Pulp Flow Dynamics Study in Three Different
Phosphoric Acid Reactors
H. Ben Abdelouahed1, J. Thereska2
1National Center for Nuclear Sciences and Technologies (CNSTN), Sidi Thabet, Tunisia
2Institute of Applied Nuclear Physics, University of Tirana, Tirana, Albania
Corresponding Author: H. Ben Abdelouahed, haifa.abdelwahed@cnstn.rnrt.tn
Radiotracers are the method of choice to diagnose the functioning of the chemical reactors
providing the most important parameters of the flow hydrodynamic and homogenization.
It is known that radiotracers are the most sensitive and accurate techniques for online
measurements of process parameters in industrial chemical reactors. Thus three different
chemical reactors for the production of phosphoric acid in Tunisian phosphate processing
plant were diagnosed by applying radiotracer method. The diagnosis of these reactors hy-
drodynamic behaviours was requested to evaluate the necessary parameters for assessment
of the current performance and for planning further action to improve their efficiency.
Tracer tests were carried out under production condition using 131I (Na131I in powder
form). The radiotracer was dissolved in some 0.5 `water and was injected at the entrance
of the reactor inside the central unit. The injection was performed instantaneously (as
Dirac pulse). Two scintillation probes (50.8 mmˆ 50.8 mm) were placed looking at the exit
pipe from reactor. Both γ-detectors were well collimated with lead shield to reduce the
influence of background radiation. The measuring time was fixed 10 s in order to detect
fast movements inside and outside the reactors, in particular to measure the flow rate of the
internal recirculation inside the reactor.
The experiment allowed a determination of the experimental RTD curves, the MRT, the
flow rate of internal recirculation, the coefficient of internal recirculation, the dead volume
rate, and identification of the mixing model corresponding to the whole reactor system
operation.
IAEA–CN–241–148 205
B03
B03-05 Talk: Session B03, Monday 17:30 Sugiharto
Residence Time Distribution Study of Geothermal Vapour Flow
in Pipe Using Axial Dispersion Modelling
S. Sugiharto1
1Centre for Applications of Isotopes and Radiation Technology, National Nuclear Energy Agency (BATAN),
Jakarta, Indonesia
Corresponding Author: S. Sugiharto, sugi@batan.go.id
In the present study, the residence time distribution of geothermal vapour phase flow
is studied using axial dispersion model. The experiment is carried out by injection of
Krypton-85 (85Kr) gas isotope into 10 inch pipe diameter containing dry geothermal vapour.
The pressure and the temperature of the vapour are 8 kg{cm2 and 170˝C, respectively.
Three collimated radiation detectors positioned respectively at 127, 177 and 277 m from the
injection point are employed to capture γ-radiation from the injected 85Kr isotope. The data
represents residence time distribution (RTD) of isotopes in the selected experimental section.
During the experiment, the flow properties are assumed to be time invariant, therefore
the flow properties are also assumed linear in character. Flow parameter calculated using
first moment method shows that the flow rate of the vapour is 11 {s. Model parameter,
represented by the Peclet number (Pe), predicted from the best fit of the axial dispersion
model to the experimental data is 223, whereas the coefficient of molecular diffusion (µ)
calculated from the Peclet number is 0.5 m2{s. The experiment concludes that the vapour
flow is dominated by convection transport and the flow pattern tends to follow plug flow
due to the big value of the Peclet number.
206 IAEA–CN–241–157
B03
Sarkar Talk: Session B03, Monday 17:45 B03-06
Radiotracer Investigation of a Pulp and Paper Mill Effluent
Treatment Plant
M. Sarkar1, V. K. Sangal1, H. Bhunia1, P. K. Bajpai1, H. J. Pant2, V. K. Sharma2, A. Kumar3,
and A. K. Naithani3
1Department of Chemical Engineering, Thapar University Patiala, Punjab, India
2Isotope Production and Applications Division (IPAD), Bhabha Atomic Research Centre (BARC), Mumbai, India
3Shreyans Industries Ltd., Ahmedgarh, Punjab, India
Corresponding Author: M. Sarkar, metali.sarkar@thapar.edu
The pulp and paper industry is highly dependent on water for most of its processes, produc-
ing a significant amount of wastewater that should be treated to environmental standards
before discharge into the atmosphere. The wastewater generated primarily consist of sub-
stantial amount of organics, inorganics, nutrients, toxic and pathogenic compounds which
are treated in an effluent treatment plant (ETP). The effluent treatment plant is a combination
of primary, secondary, tertiary and advanced treatments and vary from industry to industry
according to the process utilized. Effective performance of the ETP is crucial both for envi-
ronmental and economic view points and the radiotracer technique can be effectively used
to optimize its performance and detect anomalies like dead zones, bypassing, channelling
and so on.
A detailed residence time distribution (RTD) analysis of the aeration tank and secondary
clarifier were carried out at Shreyans Paper Ltd., Ahmedgard, was carried out using 131I as
radiotracer to detect possible anomalies in the system. The aeration tank and secondary
clarifier had capacity of 5472 m3 and 1017 m3 respectively. Flow rate of effluent water at the
inlet of aeration tank was 5.21˘ 0.1 m3{min. A pulse input of 131I was injected 18 m from
the inlet of the aeration tank and monitored using eight scintillation detectors placed at
various locations of the reactors. These detectors are attached to the data acquisition system
(DAS) using wired network that facilitated collection and visualization of the online data.
The recorded RTD data were used to evaluate the residence mean residence time (MRT).
The MRTs obtained from the experimental RTD data were found lower than their respective
theoretical MRTs. Estimated dead volume of the secondary clarifier was found to be 30%,
that indicates significant capacity of the tank is inoperative reducing its treatment efficiency.
We conclude that the radiotracer technique is a very effective tool to study complex industrial
effluent treatment plant and identifying flow anomalies in the process unit.
IAEA–CN–241–186 Presenter: V. K. Sangal 207
B03
ICARST–2017
B04:Mitigating Climate Change: Protecting Coast
Line and Environment
208
B04
Hughes Talk: Session B04, Tuesday 09:00 B04-01
Radiotracer Methods for Understanding Contaminant Dynamics
in Aquatic Environments
C. Hughes1
1Australian Nuclear Science and Technology Organisation (ANSTO), Lucas Heights NSW 2234, Australia
Corresponding Author: C. Hughes, ceh@ansto.gov.au
Radioactive tracers have a distinct advantage in tracing contaminant migration in natu-
ral systems and characterizing contaminant mobility and uptake into living organisms in
already-contaminated environments or at trace (environmental) levels. To use the contami-
nant itself in its non-radioactive form, concentrations significantly higher than the normal
contaminated background level are commonly required which may be undesirable from a
toxicological, chemical or regulatory perspective by impacting on the very processes under
study. In contrast, radioactive forms of the contaminant can often be more easily measured
(often in situ or non-destructively) and imaged at trace levels (using autoradiography), and
usually have the advantage of a short half-life to remove residual contaminant. As such
radiotracers have a valuable role to play in contaminant dynamics studies from the lab
scale to the field. In the lab, radiotracers are well established in studies of contaminant
kinetics and bio-distribution in living organisms, in interactions with non-living natural
environments, e.g., sorption to soils and sediment, rocks and organics matter, and in tracing
contaminant flow pathways and rates.
Radioisotopes of heavy metal contaminants (e.g., Cd, As, Se, Zn, Pb, Hg), nutrients (P, C)
and the shorter-lived isotopes of longer lived radioactive contaminants such as Cs and Sr
are commonly used in environmental contaminant studies. Recently, there is increasing
interest and benefit in using radiotracer versions of emerging environmental contaminants
such as persistent organic compounds or nanoparticles.
While most radiotracer work is conducted in laboratories, this approach can be up-scaled
to field environments. There are obvious scientific benefits of conducting studies in situ,
where the tracer interacts with the complex natural environment rather than an artificially
simplified laboratory representation. However there are few examples where this has been
done. Since the first field scale uses of radiotracer in the mid-1950s, the majority of field scale
radiotracer applications have been in the nexus between industry and environment sediment
transport in harbours and dams, effluent dispersion from outfalls and in mining and oil
extraction. Exceptions include whole ecosystem studies in the Canadian Experimental
Lakes in the 1970s, heavy metals downstream of a uraniummine in Kakadu NP in Australia,
and studies demonstrating the retardation of metals and nutrients in studies in Sweden.
Increasingly public and regulatory concern about the potential impact and perception of
radiotracing in field environments has made these methods appear largely inaccessible to
the research community. However, the introduction of new biota dose modelling tools and
guidelines over the past twodecades has provided improved evaluation of the environmental
impact of radiotracer releases to the environment and ensure and demonstrate their safe
use.
IAEA–CN–241–435 209
B04
B04-02 Talk: Session B04, Tuesday 09:15 Pham Van Bang
Nuclear Technologies Applied to Sediment Transport in River,
Estuarine and Coastal Zones to Validate CFD Codes
D. Pham Van Bang1
1Laboratory for Hydraulic Saint-Venant, École des Ponts ParisTech, Marne-la-Vallée cedex 2, France
Corresponding Author: D. Pham Van Bang, damien.pham-van-bang@cerema.fr
Siltation in harbours is a longstanding problem which could generate important costs for
the maintenance programme needed to secure nautical conditions. This paper reports
different studies on sediments in France (Le Havre, Bordeaux, Saint-Michel and Fort-de-
France) aiming to characterize the rheological properties of sediment, analyze sedimentation-
consolidation processes and propose a numerical model for simulating sediment dumping
and water injection dredging. Two non-intrusive techniques are used to measure the time
evolution of the vertical profile of concentration during batch settling test. The first one is a
magnetic resonant imaging (MRI) vertical prototype used on Gironde estuary. The second
is an X-ray “home-made” prototype used on the Seine estuary. Both are used to observe
the sedimentation and the consolidation processes of natural cohesive sediments that was
sampled close to Ports. They provide both movements of the supernatant/suspension
interface and the isoconcentration lines of the process. A space-time based method is
proposed to close the governing equation. Two different computational fluid dynamic
(CFD) codes are used to simulate observations in well controlled laboratory conditions. The
one is an open source and industrial 2D code (Telemac) while the other is a research and
modern 3D code (NSMP). Both are considered to reproduce sedimentation-consolidation of
very fine sediments from sites of studies with an analysis of what happens when cohesive
and noncohesive sediment are present. Even through the results are satisfying, there are
many questions arising from these exercises. More experiments (using nuclear technologies)
are therefore essential to confirm the interpretations of processes and further improve their
modelling. Since the CRP F22066 is formed, there is a new hope to tackle this longstanding
challenge.
210 IAEA–CN–241–417
B04
Bhar Talk: Session B04, Tuesday 09:30 B04-03
Radiotracer Study to Investigate the Spatial Dispersion Pattern
of Dredged Materials in Hooghly Estuary, West Bengal, India
K. Bhar1, H. J. Pant2, B. Chaudhuri3, K. Chakraborty3, and V. K. Sharma2
1Indian Institute of Engineering Science and Technology, Shibpur, Howrah, India
2Bhabha Atomic Research Centre (BARC), Mumbai, India
3Kolkata Port Trust, Kolkata, India
Corresponding Author: K. Bhar, kalyan@civil.iiests.ac.in
Maintenance of adequate draft in navigation channel for movement of ships from the sea to
the port is a serious concern for port authorities. Available draft reduces over time due to
silt deposition on the channel bed and one has to resort to maintenance dredging which
is quite expensive. The problem of silt deposition is particularly critical for riverine ports
like Kolkata and Haldia where the river and its tributaries carry large volumes of silt. The
navigational channel leading to Haldia from the Hooghly estuary requires maintenance
dredging throughout the year. The dredgers use the tidal window to dredge over the critical
shallow area in the navigation channel and then move to the dumping grounds to dispose
of the dredged materials. Effectiveness of this dredging and dumping work depends on
the location of the dumping site and the dispersion pattern of the dumped sediments,
since there is always a possibility of the disposed materials returning to the dredged site
during tides. Hence, it becomes essential to identify the pattern and rate of dispersion of the
dumped sediments, which subsequently will help in identifying proper dump site location.
With this problem in perspective, a project was undertaken to study the movement and
dispersion pattern of dredged materials near the dumping site in the Hooghly estuary via a
radiotracer experiment. Use of radioactive tracers offers a cost-effective method to deter-
mining transport of sediments caused by tidal currents and processes of erosion, transport,
settling and deposition. Radiotracers can be used to obtain quantitative information, such
as direction, velocity and thickness of sediment movement.
In this project, Scandium-46 in the form of scandium glass powder is used as the radiotracer
for tracing the dredged sediments. The tracer is prepared by incorporating 1% of inactive
Scandium in the glass composition, then grinding the glass to different grain size fractions
to have the same grain size distribution as that of the dredged material. It is then irradiated
in the reactor to produce Scandium-46. After preparation of the radiotracer, it is transported
to the the dumping site in Hooghly estuary. A specially designed remote operated injection
apparatus containing the radiotracer mixed with dredged sediments is lowered into the
water with the help of a crane and the mixture is discharged onto the sea bed. After the
injection, dispersions of the tracers were monitored using a waterproof scintillation detector
mounted on a sledge which was dragged on the seabed. The concentration at different
spatial locations are measured. This tracking work was performed during the next five
months. Isocount contourmaps are prepared from the tracking data, fromwhich the general
direction of movement of tracer is drawn and maximum longitudinal and lateral dispersion
are estimated. It is observed that the overall movement of the sediments during these five
months is away from the main navigation channel. A two-dimensional hydrodynamic
model for the study area was also developed and the velocity distribution patterns are
compared.
IAEA–CN–241–153 211
B04
B04-04 Talk: Session B04, Tuesday 09:45 Vianna Bandeira
Technetium-99m: From Nuclear Medicine Applications to Fine
Sediment Transport Studies
J. Vianna Bandeira1, L. Hannas Salim1
1Brazilian Nuclear Energy Commission (CNEN), Rio de Janeiro, Brazil
Corresponding Author: J. Vianna Bandeira, jvb@cdtn.br
Technetium 99mTc is, nowadays, the most applied radioisotope in nuclear medicine, whose
use began in the mid-1960s. Features such as emission of γ-radiation of low energy (140 keV)
with very good imaging properties, half-life τ1{2 “ 6.02 h, and production via relatively
long-lived generators, facilitating their supply and use in locations far from manufacturing
sites, were instrumental for the widespread use of the radionuclide.
However, in the aquatic environment, heavy metals and many organic compounds are
usually associated with the fine sediment phase (silt, clay, or mud). The fate of these contam-
inants will be associated with the dynamic behaviour of suspended or bottom sediments in
polluted streams. The study of suspended sediment behaviour is central to many environ-
mental studies. Of special interest is the study of individual discharges of contaminants
associated with suspended sediments, the short-term dispersion of contaminated material
dredged from harbours and reservoirs when dumped into water bodies and the behaviour
of natural sediment in suspension in bays, estuaries or reservoirs. Tracking for few hours of
the contaminated suspended sediments introduced into streams or in the coastal area by
individual discharges could allow the quantitative in situ determination of the advection,
dispersion, dilution and sedimentation rates, parameters important for the calibration and
validation of hydrodynamic models that comprise both the solid and liquid phases.
Radioactive tracers, in appropriate chemical form, are used to label fine sediment by chemical
sorption, and some (such as 198Au and 51Cr) have been employed to study the dynamics
of fine sediment in suspension. But these tracers have to be produced in nuclear reactor
each time they are used and require heavy shielding due to the dense flux of high-energy
γ-radiation they emit, which hampers their use in remote areas.
Given the favourable characteristics of 99mTc, the feasibility of its use for labelling mud,
through the chemical reduction of the TcO´4 eluted from Mo/Tc generators, was studied in
laboratory with regard to the following aspects: 1) labelling yield as function of different
factors (type and amount of reductant; effect of pH; sediment concentration; contact time;
labelling stability); and 2) hydrodynamic behaviour of labelled and nonlabelled sediment,
through sedimentation tests. The laboratory tests were successful and this new use of the
99mTc allowed already interesting results obtained in various applications: Montevideo Bay
(Uruguay), Pampulha Hydrographic Basin (Brazil), Orinoco River (Venezuela), environmen-
tal impact due to the fine sediment originated from bottom discharge of small hydroelectric
power plant (Brazil), etc.
The work performed in some field applications used second week generators obtained,
at no cost, from Nuclear Medicine laboratories. The reason is that the 99mTc detector
for environmental applications is placed into the water, in 4π geometry and for medical
applications it is situated externally to the patient. So, the necessary activity concentrations
for environmental use (Bq/m` in water) are much lower (10´7) than in nuclear medicine
utilization (Bq/m` in blood).
212 IAEA–CN–241–175
B04
Terrier Talk: Session B04, Tuesday 10:00 B04-05
The Use of Nucleonic Gauge JTTX in the Port of Nantes
Saint-Nazaire
P. Terrier1, P. Brisset2
1Grand Port Maritime de Nantes Saint-Nazaire (GPMNSN), Saint-Nazaire, France
2International Atomic Energy Agency (IAEA), Vienna, Austria
Corresponding Author: P. Terrier, p.terrier@nantes.port.fr
There is a continuous sedimentation in harbour basins and access channels, therefore
maintenance dredging is necessary. The depth necessary for sailing includes the free
space between the keel and the bed of the channel called keel-clearance. Tests on physical
models indicated that free movement of ships in the harbour is possible up to silt density
1.2 g/cm3. The layer of fluid mud (silt) where the density equals 1.2 g/cm3 is defined as
“sea bed”. This layer shifts upwards with time due to deposition resulting in decrease in the
“nautical depth”. To keep the required nautical depth it is necessary to measure the depth
periodically, usually measured using an echo sounder. The upper trace recorded by the echo
sounder is taken as the bottom of the channel. It is misleading in the case of channels with
muddy bottoms. In these conditions the echo sounder readings cause excessive dredging
adding extra cost. This can be avoided by the measurement of sediment density at different
depths. To effectively determine when and how dredging operations must be undertaken,
the underwater sediment and mud layers must be monitored and analyzed. This paper
presents an innovative vertical profiling technique measuring the density versus depth of
the sediment layer. The instrument uses X-rays to measure the sediment density and has
been developed by the French Atomic Energy Commission and ALTAIX Cie.
The information is used for two important aspects:
1. The quality control of dredging works where the data is used to determine the dry
matter content of the dredged material and to know precisely the real solid matter
removed during the dredging operation;
2. In combination with echo-sounding survey methods, it is used for optimizing the
dredging works based on the concept of navigability depth limit. Ships can operate
through loose mud layers if the physical characteristics of the mud stay below a
critical limit.
Nowadays the measured physical characteristic in many ports is density. The navigability
depth limit is usually corresponding to the density 1.2 g/cm3. The proposed measurement
technique allows visualization of density and enables ports to evaluate nautical depth
criteria. Dredging only when the navigability depth limit is above the navigation depth
allows very important savings.
The paper will present the operation of the gauge in the Port of Nantes Saint-Nazaire, France.
IAEA–CN–241–345 Presenter: P. Brisset 213
B04
B04-06 Talk: Session B04, Tuesday 10:15 Suárez-Antola
Water Renewal in Montevideo’s Bay II: A Compartmental
Fractional Model for Tritium Kinetics
R. Suárez-Antola1
1Asesor, Ministerio de Industria, Energía y Minería, Uruguay
Corresponding Author: R. Suárez-Antola, robertosua@gmail.com
This paper describes the construction of a new compartmental fractional model for water
renewal in Montevideo’s Bay that improves a conventional two compartments model r1s.
The validity of the fractional kinetic model and its practical applicability are discussed.
The available evidence suggests that the highly polluted Montevideo bay operates as an
intermittent tidal pump that injects contaminants in the nearby coastal waters, with potential
effects on the beaches located east to the bay’s mouth. In order to assess this effect, several
field studies were done in the bay itself and in the adjacent coastal waters covering water
and sediments dynamics r2s. In the framework of a field research of the dynamics and
renewal of water in Montevideo Bay, 3.7ˆ 1012 Bq of tritiated water were evenly distributed
in the north-east region of the bay, during five hours of continuous injection. The whole
bay was divided in 20 concentration cells, taking into account available bathymetric data
and corrections from field data obtained in situ. Tritium concentrations (activity per unit
volume) and other relevant parameters (temperature, electrical conductivity, etc.) were
measured in vertical profiles during three weeks, in the mid-point of each cell, first twice
a day and then on a daily basis. Remnant total tritium activity was estimated from cells
volumes and midpoint cells activity concentrations. The details of the measured tritium
kinetics, available bathymetric data, water movements in a tidal environment measured
with drogues, fluorescent tracers and current meters, as well as the results of computer
fluid dynamics modelling (averaged in depth), suggests that in a first approximation the
bay can be meaningfully divided in two main compartments: a North-East and a South-
West compartment. The time course of the tail of the tritium remnant function suggests
the use of fractional calculus to model the process of water renewal. The conventional
two compartments model is generalized by the introduction of fractional derivatives (in
Caputo’s sense) following a procedure that does not violate mass balance r3s. Fractional
order parameters are estimated from available experimental data and the measured time
evolution of the tracer remnant function is explained. The wash-out kinetics from the bay of
toxic chemical substances or dangerous microbial populations, introduced after a sudden
contamination accident in the harbour, is described using the fractional compartment model
and additional information from CFD simulations.
References
r1s A. R. Suárez, “Water Renewal in Montevideo’s Bay I: A Two Compartments Model for
Tritium Kinetics”, 2013 International Nuclear Atlantic Conference, INAC 2013, Recife,
Brazil (2013), DOI: 10.13140/2.1.2675.2005.
r2s A. R. Suárez, “Tracer Studies in the Coastal Waters of the Department of Montevideo”,
Proceedings of the Eight Meeting of the International Centre for Earth Sciences, Mar del
Plata, Argentina (2012), DOI: 10.13140/2.1.3461.6322
r3s A. Dokoumetzidis, R. Magin and P. Macheras, “A Commentary on Fractionalization of
Multi-Compartmental Models”, J. Pharmacokinet. Pharmacodyn., 37, 203–207 (2010).
214 IAEA–CN–241–053
B04
Ioannidou Talk: Session B04, Tuesday 10:30 B04-07
The Radiotracer 7Be in Studying Environmental Processes
A. Ioannidou1, A. Vasileiadis1, and D. Melas1
1Physics Department, Aristotle University of Thessaloniki, 54124 Thessaloniki, Greece
Corresponding Author: A. Ioannidou, anta@physics.auth.gr
The objective of the study is to define the time delay between the tropopause elevation
and the concentration of the radiotracer 7Be in near-surface air in order to understand the
aerosol transport inside the troposphere as a part of the general atmospheric cycle transfer.
The relatively short-lived 7Be radionuclide (τ1{2 “ 53.3 d) of cosmogenic origin occurs
permanently in the atmosphere. It is formed continuously by the interactions of cosmic-
ray particles with atmospheric nitrogen and oxygen. The 7Be production rate depends
primarily on latitude, altitude and the 11-year solar cycle and has been proved powerful
tool in studying atmospheric processes.
The concentrations of 7Be in the troposphere and near ground level show variations which
are connected with air mass exchange between the stratosphere and the troposphere, in
situation of tropopause folding events. Air coming from the upper troposphere or from
stratosphere can be identified by its enhanced 7Be levels.
The tropopause marks the boundary between troposphere and stratosphere. The height of
tropopause is variable in space and time, because of the latitudinal and seasonal dependence
of solar irradiation as well as the changes due to weather patterns. There is a well-marked
“tropopause gap” or break where the tropical and polar tropopause overlap at 30˝–40˝
latitude. The break is in the region of the subtropical jet stream and is of major importance
for the transfer of air and tracers (humidity, ozone, radioactivity) between stratosphere and
troposphere. The height of the tropopause varies seasonally and also daily with the weather
systems.
The current study presents an analysis of 7Be data at geomagnetic latitude of 40˝. The pre-
sentation will show the pattern of the cross-correlation analysis of 7Be surface concentration
values and tropopause height, revealing that after the third day the correlation coefficient
falls dramatically. The Rmax was found in the third day (« 0.44). The study revealed that
the concentration of 7Be in surface air is expected to correspond within 3 days after the
changes of the tropopause height. Moreover, measurements and calculations throughout
the research were extremely beneficial in a variety of ways and led to the following findings:
• The verification of the yearly variations of the tropopause height in mid attitudes.
• The understanding of aerosol transport inside the troposphere as a part of the general
atmospheric cycle transfer.
• That the persistence in the state of the atmosphere cannot be ignored.
• Temperature and tropopause height indicate the time of transport of a useful tracer
radioactive nucleus through air transfer cycles and as a consequence of any other
aerosol particle with similar origin inside the tropopause.
• Higher values of temperature or tropopause height result to shorter transport times.
IAEA–CN–241–065 215
B04
ICARST–2017
B05:Radiotracers for Energy of the Future I
216
B05
Toukan Talk: Session B05, Tuesday 11:15 B05-01
Liquid Holdup Studies in a Co-current Gas-Liquid Upflow
Moving Packed Bed Reactor with Porous Catalyst Using γ-Ray
Densitometry
A. Toukan1, V. Alexander1, H. Al-Bazzaz2, and M. Al-Dahhan1
1Department of Chemical & Biochemical Engineering, Missouri University of Science & Technology, Rolla, MO
65409, USA
2Kuwait Institute of Science Research, P.O. Box 24885, 13109 Kuwait
Corresponding Author: A. Toukan, ajt5yc@mst.edu
Upflow moving packed bed reactors are widely used in industries for hydrotreating like
hydrodenitrogenation, hydrodesulfurization, hydrodemetallization, etc. In these reactors,
deactivated catalyst are removed from the bottom, and fresh catalyst are added from the top,
gas and liquid phase move concurrently upwards. The catalyst removal occurs only once in
a week and that too in small increments. Some of the common problem associated with
this reactor are maldistribution, hot spot, and reduced expected conversion. To overcome
these challenges, detailed study to enhance the understanding of hydrodynamics in this
reactor is still required. In this work line-average liquid holdup is determined using γ-
ray densitometry (GRD) in a scaled down lab scale upflow packed bed column. γ-ray
densitometry is a noninvasive radioactive technique and can be implemented to monitor the
flow distribution even at industrial scale. There are no studies reported on determination of
line average phase distribution for packed bed with the porous catalyst using GRD. In this
study, a new methodology has been developed to determine the line average liquid holdup
for a porous catalyst. Which gives the line average holdup in the void space of catalyst
bed plus the line average internal porosity of catalyst. This study has been conducted on a
Plexiglas column of 112 ID ( “ 279.4 mm) and 302 height (“ 762 mm), randomly packed
with extrudate catalyst of 3 mm diameter until 242 height (“ 610 mm). GRD scanning is
conducted at various axial and radial locations. The line average liquid holdup is determined
at superficial liquid (water) at 0.017 cm/s and varying superficial gas (air) velocity in the
range of 0.6–7.7 cm/s. The results show that the liquid holdup decreased as the superficial
gas velocity increased. It was also found that the liquid holdup radial distribution was not
uniform. This kind of information is essential to improve the performance of the reactor.
IAEA–CN–241–019 Presenter: M. Al-Dahhan 217
B05
B05-02 Talk: Session B05, Tuesday 11:30 Alexander
Bed Expansion Studies in UpflowMoving Catalytic Packed/
Expanded Bed Hydrotreating Reactor Using γ-Ray Densitometry
V. Alexander1, H. Al-Bazzaz2, and M. Al-Dahhan1
1Department of Chemical & Biochemical Engineering, Missouri University of Science & Technology, Rolla, MO
65409, USA
2Kuwait Institute of Science Research, P.O. Box 24885, 13109 Kuwait
Corresponding Author: V. Alexander, vaxt8@mst.edu
Upflow moving catalytic packed or expanded bed reactors are widely used in industries for
hydrotreating of feeds with a higher level of contaminants including heavier feeds. In these
reactors, spent catalyst are replaced periodically by adding fresh catalyst at the top and
removing spent catalyst from the conical bottom which supports the catalyst bed. While
the catalyst moves downwards periodically, the gas and liquid phase moves upwards. The
catalyst is removed in small increments once a week. The other times the reactor operates
in upflow packed or expanded bed condition. The problem associated with these reactors
is maldistribution, which causes hotspots, sintered carbon deposition and reduces expected
conversions. It is seen that the main reason for these issues is maldistribution of phases
at the local level inside the catalyst bed region. Bed expansion plays a huge role in local
flow distribution of phases. In these reactors the expanded bed region gives the better
radial distribution of phases, but less overall mixing intensity of phases as compared to
packed bed region. Furthermore, the movement of catalyst particle in the expanded bed
profoundly affects reaction kinetics in these areas. It is seen that under industrial best-
operating conditions of these reactors the catalyst beds exhibit packed and expanded bed
regions. Expanded bed can be seen at the top part of the bed. There are no studies done yet
to demarcate the expanded and packed bed region.
In this work, quantification of bed expansion will be done on scaled down lab scale reactor
by online monitoring with γ-ray densitometry (GRD) along the bed height. The time series
data obtained from GRD will be analyzed to identify flow regime, and variation in flow
regime trends between packed bed with expanded bed region will be used to demarcate the
boundary. The analysis of time series are done on time domain (standard deviation, mean,
and variance), frequency domain (power spectrum, wavelet analysis) and chaotic analysis
(Kolmogorov entropy (KE)). We focus in this work on the catalyst bed section, which is
a Plexiglas column of 112 ID ( “ 279.4 mm) and 302 height (“ 762 mm), filled with
extrudate catalyst of 3 mm diameter until 242 height (“ 610 mm). The measurements were
conducted at superficial liquid (water) velocity of 0.017 cm/s to 1.78 cm/s and superficial
gas (air) velocity of 1.27 cm/s to 8.8 cm/s. This kind of information is essential at industrial
scale, for efficient design and operation of these reactors. In this presentation, results and
findings are discussed.
218 IAEA–CN–241–018
B05
Sheoran Talk: Session B05, Tuesday 11:45 B05-03
Radioactive Tracing of an Industrial Scale Continuous Pulp
Digester
M. Sheoran1, A. Chandra1, H. Bhunia1, H. J. Pant2, J. Biswal2, P. K. Bajpai1, and S. Rao3
1Department of Chemical Engineering, Thapar University, Patiala 147004, Punjab, India
2Isotope Production and Applications Division (IPAD), Bhabha Atomic Research Centre (BARC), Mumbai, India
3Satia Industries Limited, Sri Muktsar Sahib 152101, Punjab, India
Corresponding Author: M. Sheoran, mmmeenu.50@gmail.com
The Indian paper industry has an approximately 2.6% share of global paper production
from „ 813 paper mills. The chemical pulping process is widely used to produce paper
using different types of raw material such as wood, bagasse, agro residue (wheat straw, rice
straw) etc. The raw material is directly fed to a pulp digester along with white liquor to
produce pulp. The pulp obtained from the digester is used to manufacture various types of
paper including writing paper, printing paper, packing paper, etc. The performance of the
pulp digester is very crucial for product yield, product quality, overall operating cost and
waste generation. Hence, it is important to understand the flow behaviour/ hydrodynamics
of the pulp digester to optimize operating variables.
The industrial scale experiments were conducted for radioactive tracing of three tube con-
tinuous pulp digester in Satia Industries (India) using radioisotopes 82Br and 198Au. The
tube length and diameter of single tube of pulp digester is 12 m and 1.45 m respectively.
Wheat straw and white liquor were fed to the digester at 157–169˝C temperature and 5.39–
6.45 kg/cm2 pressure. The white liquor was fed at the rate of 360 `{min and wheat straw
was fed at feeder screw speed of 65 rpm. The radiotracer was injected at the inlet of the pulp
digester using a high pressure pump. Four radiation detectors were used to record the radio-
tracer concentration at the inlet and outlet of each individual digester tubes. The recorded
radioactive signals were compared and used to elucidate the residence time distribution,
mean residence time (MRT) and flow behaviour of pulp digester.
Approximate 20% difference were found in MRTs of 198Au and 82Br. The higher value of
MRTs for 198Au than 82Br indicating some adsorption of 198Au on wheat straw. MRTS for
198Au is representing MRTs of bulk flow (pulp), whereas MRTs using 82Br represent MRTs
of liquid phase only. The segregated, erratic and inhomogeneous flow were observed in
first digester tube. The axial dispersion model with plug flow component in series were
found suitable for both cases. The non-dimensional axial dispersion coefficient for third
digester tube were found as 270 and 250 for 198Au and 82Br, respectively.
The present radiotracer technique is foundwell suited for tracing of the pulp digester even at
high temperature and pressure to identify the malfunctioning such as back-mixing, reverse
flow, bypassing and stagnation volume of pulp digester, etc. This technique can be used for
locating the leakage, fouling or other abnormalities.
IAEA–CN–241–057 Presenter: A. Chandra 219
B05
B05-04 Talk: Session B05, Tuesday 12:00 Aquino
Evaluating the Operating Conditions of a Rectifier Column
Using γ-Column Scanning
D. Aquino1, J. Mallillin1
1Philippine Nuclear Research Institute (PNRI), Quezon City, Philippines
Corresponding Author: D. Aquino, ddaquino@pnri.dost.gov.ph
This paper reports the γ-scanning carried out to a rectifier column in one of the refineries
in the Philippines. Several scans were performed to gather information on the operating
conditions of the column at different sets of operating parameters using a 10 mCi 60Co
source and a 22 (50.8 mm) detector tandem. Results of each scan reveal the presence of
blockages at several sections of the column. These blockages cause flooding inside the
column when process settings were changed as reflected in the profiles of several scans.
γ-column scanning was able to specify the presence and location of blockages and their
effect to the operating condition of the column at varying process parameter settings.
220 IAEA–CN–241–287
B05
Nguyen Huu Talk: Session B05, Tuesday 12:15 B05-05
γ-Scanning Technique as an Efficient Investigation Tool for
Diagnostics and Troubleshooting in Industry: Case Studies
Q. Nguyen Huu1, M. Tran Thanh1, T. D. Dang Nguyen1, and C. T. Mai1
1Centre for Applications of Nuclear Technique in Industry (CANTI), Dalat City, Lamdong Province, Viet Nam
Corresponding Author: Q. Nguyen Huu, nhquang.dalat@gmail.com
In nuclear technique applications in industry, γ-scanning is recognized as a simple but very
common and useful on-line investigation technique for diagnostics and troubleshooting.
Based on the principle of attenuation of γ-beam intensity according to the density of mate-
rial while penetrating through the object, γ-scanning provides data or information about
situation of components such as pipe, columns to optimize the performance or to identify
maintenance requirement.
Among a number of applications carried out by CANTI, this paper gives the typical case
studies of use of γ-scanning to detect damage, pipeline blockage and to investigate malfunc-
tions in process columns in the petroleum refinery which provided technical evidence to
engineers for repair planning.
γ-column scanning was used to determine a malfunction in the flue gas absorber tower of
Dungquat Refinery. The scanning results showed a heavy foam occurred in many trays that
helped the operator to adjust the operational parameters to recover normal performance
whichwas confirmed by a followup re-scanning. In other applications of γ-column scanning,
the inside situation of columns such as tray damage, flooding, deformation of tray and so
on, was also detected in preparation for maintenance.
In pipelines, the γ-scanning technique was used to detect the blockage inside flare pipeline,
to inspect the damage of refractory inside the withdrawing well and to detect a part of a
steel valve dropped and stuck inside a steam pipeline.
In many cases, γ-scanning was the only technique capable of solving problem owing to the
high penetration capability of γ-ray through the thick steel wall of components, permitting
internal inspection; and implementation of the online inspection without shutting down
the process.
IAEA–CN–241–117 221
B05
B05-06 Talk: Session B05, Tuesday 12:30 Dagadu
Validation of CFD Codes Using Radiotracer RTD Analysis of
Stirred Vessels
C. P. K. Dagadu1
1Ghana Atomic Energy Commission (GAEC), Legon-Accra, Ghana
Corresponding Author: C. P. K. Dagadu, dagadukofi@yahoo.co.uk
Radiotracer residence time distribution (RTD) and computational fluid dynamics (CFD)
are two methods (experimental and numerical) that can be used to study the performance
of industrial process reactors. Although all the required parameters of a process vessel
can be found using RTD methodology, experimental results should be used to validate
CFD codes. CFD simulations not only makes the design of flow systems much easier but
also better explains the system’s flow structure. The aim of the investigation was to used
results obtained from a radiotracer RTD analysis of stirred vessels to validate CFD codes.
The flow field in the vessel was simulated using CFD multiphase and turbulence models.
The simulated flow field was used generate the RTD using a Lagrangian particle tracking
method. The simulated RTD curves and mean residence time were in good agreement with
experimental results.
222 IAEA–CN–241–323
B05
ICARST–2017
B06:Radiation Techniques for Energy of the Future
223
B06
B06-01 Talk: Session B06, Tuesday 14:15 Derivet
The γ-Scanner: A Tool for the Quality Control of the Process of
Alcohol Distillation
M. Derivet1, I. M. Fernández Gómez1, J. A. Carrazana González1, E. A. Capote Ferrera1,
J. Flores1, J. Cuesta Borges1, and J. Martínez Valdés1
1Center for Radiation Protection and Hygiene (INHEM), Havana, Cuba
Corresponding Author: M. Derivet, derivet@cphr.edu.cu
γ-scanning is a technology management tool to increase manufacturing efficiency. Modern
industrial production requires strict process control, in order to meet established quality
standards. The technique of γ-ray scanning allows non-destructive diagnosis, which has
among its applications the study of distillation columns. The method is based on the
different degree of attenuation of γ-radiation as it passes through materials of different
density. Through the analysis of a vertical density profile, it is possible to identify function-
ing problems without stopping the industrial process under study, and without physical
intrusion. This improves the operational efficiency and reduces the time for maintenance.
The present paper shows the results of a study conducted applying the technique of γ-ray
scanning to a distillation column of alcohol from the distillery “Hector Molina”. The study
revealed the presence of some small anomalies such as the presence of foam in some regions
of the distillation column. The identification of these anomalies contributed to efficiency
improvements of the tower, improving as a consequence the quality of the obtained alcohol,
and contributing to the environmental management system that should be associated to the
process of alcohol distillation
224 Presenter: I. M. Fernández Gómez IAEA–CN–241–002
B06
Abd El Slam Talk: Session B06, Tuesday 14:35 B06-02
A NewMethod for Detecting Trace Oil Concentration by
Neutron Radiography Technique
T. Abd El Slam1
1Egyptian Atomic Energy Authority (EAEA), Cairo, Egypt
Corresponding Author: T. Abd El Slam, tmongy@gmail.com
The modern neutron imaging (NI) facility in the ETRR-2 provided precise information for
detection of trace oil concentration in cultural heritage treasures. The presence of high
scattered oil materials distorted the neutron radiography quantitative measurements and
caused blurred images.
This work presents a new technique in precise quantitative measurement and calibration.
The technique was based on the scattering correction of images. The correction was not
based on the Monte Carlo (MCNP) code simulations, but rather on a real case scattering
correction by a designed code. Also, the distinction of this work was showing a real free
scattered image that was not performed before.
The designed code possesses an extensive set of algorithms for digital image processing. The
code has arithmetic menu commands performing versatile operations between images. The
installation of the excellent neutron imaging system at the research reactor in Egypt increased
the reliance on appropriate software for advanced imaging processing anddata analysis. The
code provided up-to-date high quality images by designing formula commands supported
by all standard mathematical functions. This open source code was used for detection and
measurement of trace oil concentration by the neutron radiography (NR) technique.
IAEA–CN–241–308 225
B06
B06-03 Talk: Session B06, Tuesday 14:55 Sebastian Calvo
Leaks Determinations in Reboilers from Natural Liquid
Fractioning Units
C. Sebastian Calvo1
1Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), São Paulo, Brazil
Corresponding Author: C. Sebastian Calvo, csebastian@ipen.gob.pe
In recent years, IPEN has developed various techniques based on the application of tracers
and radiation sources to solve problems operating facilities oil refining and gas.
The objective of the experiments was to identify leaks and passes in reboilers, either thermal
fluid or hydrocarbon products in the reboiler of a depropanizer column, in the reboiler of a
debutanizer column and, in the reboiler of a stripping column from a fractionation column
naphtha-diesel. A set of determinations are reported with various radiotracers experiments
in reboilers from natural liquid fractioning units, for leaks / passes that could exist in three
reboilers.
The tracer technique for online detection was used, by using two radiotracer depending on
the phase to be investigated: oleic acid labelled with 131I as a radiotracer for the hydrocarbon
phase and an aqueous solution of 133I for the aqueous phase, when necessary. A data acqui-
sition system, a portable PC, and detectors in proper positions were used. Recording values
were synchronized as well as ambient background, prior to each injection of radiotracer.
Radiation counts were recorded at 1 s intervals in each case.
Six determinations were conducted by six injection of radiotracer incorporated, either in
tubes or shell, as applicable. We achieved detection limits leakage of 0.1%, of one stream to
another.
226 IAEA–CN–241–437
B06
Sabri Talk: Session B06, Tuesday 15:15 B06-04
RPT for Tracking Microalgae Cell Movement in Split
Photobioreactor Column
L. Sabri1, A. Sultan1, and M. Al-Dahhan1
1Department of Chemical & Biochemical Engineering, Missouri University of Science & Technology, Rolla, MO
65409, USA
Corresponding Author: L. Sabri, lssf25@mst.edu
Radioactive particle tracking (RPT), is a visualization technique utilized for multiphase
flow systems. This technique has been used to track microalgae cells movement through
all the segments of growth by tracking a single radioactive particle (200 µCi of 60Co). This
particle was coated by 2 mm polypropylene particle to mimic the motion of the liquid inside
the reactor. The γ-ray intensity distributions were revealed by 30 NaI detectors placed
uniformly around the reactor at specific angles and levels. The performance of the split
photobioreactor requires in-depth knowledge and understanding for photosynthetic growth
and for hydrodynamic parameters: the advanced non-invasive measurement technique of
radioactive particle tracking (RPT) will provide that information.
This present study investigates the flow features in the 5.52 (140 mm) inner diameter Plex-
iglas split photobioreactor for air-green algae (Scenedesmus) system. Moreover, it seeks
to examine the impact of algae growth rate on the three-dimensional liquid velocity field
and turbulent parameters (Reynolds stresses, turbulent kinetic energy, and turbulent eddy
diffusivities) at different superficial gas velocities (1, 2, and 3 cm/s). The experimental
results will provide benchmark data for simulation, design, scale-up, and performance
calculation of the split photobioreactor. The experimental results and conclusions will
present at the conference.
IAEA–CN–241–021 227
B06
B06-05 Talk: Session B06, Tuesday 15:35 Toukan
Flow Regime Identification in a Co-Current Gas-Liquid Upflow
Moving Packed Beds Reactor Using γ-Ray Densitometry
A. Toukan1, V. Alexander1, H. Al-Bazzaz2, and M. Al-Dahhan1
1Department of Chemical & Biochemical Engineering, Missouri University of Science & Technology, Rolla, MO
65409, USA
2Kuwait Institute of Science Research, P.O. Box 24885, 13109 Kuwait
Corresponding Author: A. Toukan, ajt5yc@mst.edu
In industries, upflow moving packed bed reactors are widely used as guard reactors for
residual desulfurization units (RDS). Efficient reactor function has a huge impact regarding
efficiency and product quality from the subsequent RDS units. Identification of flow regimes
is one of the important aspects of design, scale up, predictivemodel and reactor performance.
Flow regime identification in this reactor was studied using γ-ray densitometry (GRD).
GRD is an important noninvasive measurement technique and flow identification can be
determined by on-line monitoring. Time domain, frequency domain, and state space or
chaotic methods are employed on photon count time series of GRD to determine flow regime.
Time domain analysis includes determination of standard deviation, mean, and variance.
Frequency domain analysis includes power spectrum andwavelet analysis. Chaotic analyses
include determination of Kolmogorov entropy (KE). All analysis are done using in-house
developed programmes.
GRD experiments were performed on a lab scale upflow packed bed reactor built by scaling
down the industrial reactor. The lab scale reactor is a Plexiglas column of 112 ID ( “
279.4 mm) and 302 height (“ 762 mm), randomly packed with extrudate catalyst of 3 mm
diameter until 242 height (“ 610 mm). Various axial and radial position are selected to
conduct GRD scanning. The selected test location covers the bottom, middle and top of
the packed bed. The measurements are conducted at superficial liquid (water) velocity
0.017 cm/s and superficial gas (air) velocity in the range of 0.6–7.7 cm/s. All analysis
showed similar flow regime trend. When compared with flow regime map for upflow
packed bed, the results indicate bubbly and pulse flow are the main regimes under this
operating conditions. In this presentation, results and findings are discussed.
228 IAEA–CN–241–020
B06
ICARST–2017
B07:Radiotracers for Energy of the Future II
229
B07
B07-01 Talk: Session B07, Tuesday 16:30 Idiri
Simulation and Optimization of a Neutron Backscattering
Analysis Set-Up Using MCNP5 Code
Z. Idiri1, N. Taibouni2, N. Belouadah2, and H. Mazrou1
1Centre de Recherche Nucléaire d’Alger (CRNA), Alger-Gare, Algeria
2Université des Sciences et de la Technologie Houari Boumediene, Bab Ezzouar Alger, Algeria
Corresponding Author: Z. Idiri, idiridz@yahoo.fr
A neutron back scattering set-up for analysis of hydrogenous sample materials has been
simulated using MCNP5 neutron and photon transport code. The set-up is mainly com-
posed of an Am-Be neutron source of 37.2 GBq and a 3He neutron gas detector which are
embedded in polyethylene block, the latter acting as a reflector. The modellization used
in the simulation was validated comparing thermal neutron flux calculated values with
measured ones using indium activation foils and 3He neutron detector. Then, calculations
were carried out to determine optimal dimensions of the reflector and the sample holder
with the constraint that the neutron and γ-doses must be at acceptable levels. We have also
studied the response of the set-up for other reflector materials such as wax and Perspex.
Finally, the analysis of organic samples was simulated and the calibration curves were
determined for hydrogen and (C`O/H) ratio. The simulated calibration curves were then
compared with those experimentally determined
230 IAEA–CN–241–342
B07
Jung Talk: Session B07, Tuesday 16:45 B07-02
RPT Study on a Vertical Impeller Mixer
S.-H. Jung1, J.-H. Moon1, and J.-G. Park1
1Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
Corresponding Author: S.-H. Jung, shjung3@kaeri.re.kr
Radiotracer techniques have been widely applied in various fields of industry in order to
diagnose plant processes during operation. This is possible because radioisotopes can selec-
tively label certain process media and represent their movements. Recently, radioisotopes
have been successfully used as tracers in the investigations for clarifiers and digesters in
wastewater treatment plants. Quantitative information about the performance and flow pat-
terns of digesters and clarifiers were obtainedwithout posing any disturbance to the systems
themselves. More recently, studies were conducted to show the feasibility of radiotracer
techniques in investigating the particle velocity in fluidized bed reactors compared with the
techniques based on optical fibre probes and borescopic particle image velocimetry r1s. It
has been well described that radioisotope technologies are somewhat superior to others
in terms of the limitations in the measurements caused by the signal cross-correlation and
minimum measurable flow velocity and vertical angle. CFD simulations on a digester with
an internal airlift loop were performed to study the influence of the geometric design on
the flow pattern, location of circulation and stagnant regions, liquid velocity profiles, and
volume of dead zones, and are subsequently compared with experimental data obtained
by radioactive particle tracking r2s. CFD simulations must be developed for individual
situations because multiphase systems have very complicated physics and are difficult to
fully understand. Once the CFD predictions are validated with experimental measurement
data, the predicted hydrodynamic parameters can be quantified and used in the design
selection and optimization of systems r3s.
A vertical impeller devised to move up and down along the axis of a cylindrical digester
is believed to generate a mixing flow inside, saving the energy for operating the process
since the downward movement can be accomplished with the gravitational force. However,
the flow pattern and mixing characteristics as a function of the operation parameters of the
vertical impeller have not been investigated. In a preliminary study, a radiotracer experiment
was carried out for a pilot-scale digester equipped with a vertical impeller. Unfortunately,
tomographic measurements that can reveal the flow in 2-dimensions cannot be applied
due to the size of the digester. The flow was roughly guessed from the data collected from
radiation probes installed inside the digester. In the present paper, as a subsequent study, a
smaller lab-scale digester was built for further tomographic investigations. Radiotracers
were injected into it for SPECT and RPT studies that provide local information on the flow
and multidimensional visual images.
References
r1s S. Tebianian, et al., Chem. Eng. Sci., 127, 310–322 (2015).
r2sM. S. Vesvikar and M. Al-Dahhan, Biotechnol. Bioeng., 89, 719–732 (2005).
r3s S.-H. Jung, et al., Appl. Rad. Isotop., 70, 2471–2477 (2012).
IAEA–CN–241–028 231
B07
B07-03 Talk: Session B07, Tuesday 17:00 Sultan
Linear Attenuation Coefficients and Gas Holdup Distributions of
Bubble Column with Vertical Internal Bundle for FT Synthesis
A. Sultan1, L. Sabri1, and M. Al-Dahhan1
1Department of Chemical & Biochemical Engineering, Missouri University of Science & Technology, Rolla, MO
65409, USA
Corresponding Author: A. Sultan, ajshw9@mst.edu
Linear attenuation coefficient distribution, time-averaged cross-sectional gas holdup dis-
tribution, and their radial profiles have been measured in 62 (152 mm) Plexiglas bubble
columns with and without internals for the air-water system at a superficial gas velocity
45 cm/s by utilizing a γ-ray computed tomography (CT) technique. Several 12 (25.4 mm)
diameter Plexiglas internals cover 25% of total column cross-section have been installed in
the column, similar to those using for Fischer-Tropsch (FT) synthesis.
The experimental results revealed that the reference scan significantly affects the values
of the linear attenuation coefficients and consequently the gas holdup distribution images.
The results show that using air (no column) as a reference scan, enhances the accuracy of
linear attenuation coefficients and hence the precision of gas holdup results, while using the
empty column with internals as a reference scan gives incorrect values for linear attenuation
coefficients and gas holdup values. Moreover, using air (no column) as a reference scan had
eliminated the error in gas holdup profiles in the wall region. Furthermore, the CT scan
images exhibit symmetric gas holdup distributions for bubble columns with and without
internals as studied for the superficial gas velocity. Finally, the γ-ray computed tomography
technique was capable of capturing the wall thickness of a column and position of each
internal when air (no column) is used as reference scan.
232 IAEA–CN–241–022
B07
Ouardi Talk: Session B07, Tuesday 17:15 B07-04
Numerical Simulation of Measurement by γ-Ray Scanning of
Coke Deposition in Packed Bad of Distillation Column
A. Ouardi1, R. Alami1, A. Saadaoui1, R. Outayad1, and F. Z. Oujebbour1
1Centre National de l’Energie des Sciences et des Techniques Nucléaires (CNESTEN), Rabat, Morocco
Corresponding Author: A. Ouardi, ouardi@cnesten.org.ma
In distillation columns, the packed column for gas-liquid contacting are used extensively
for absorption, stripping and distillation operations. A principal problem encountered in
operating a packed bed is the coke disposition which is related to both process condition
and structural problems. As the γ-scanning technique is adequate to define on-line trou-
bleshooting, in the present study, we try to define by Monte Carlo numerical simulations
the minimum rate of coke deposition in the packed bed that can be revealed by this tech-
nique. Such information assists engineers in troubleshooting process problems, optimizing
production and minimizing plant down time.
A simple packed bed geometry was reproduced in the numerical model, with different coke
deposition rates. The preliminary simulation results show that it is possible to detect coke
deposition for coke occupation volume higher than 7.3% compared to the packed bed total
volume. The second part of this work will be dedicated to define an optimal configuration
of γ-scanning to provide accurate measurements of the coke deposition rate taking into
account the coke.
IAEA–CN–241–282 Presenter: R. Alami 233
B07
B07-05 Talk: Session B07, Tuesday 17:30 Roy
Noninvasive Radiation Based Densitometry and Velocimetric
Monitoring of Fluidization of Coal and Bottom Ash Mixtures
S. Roy1, H. J. Pant2, and S. Roy1
1Indian Institute of Technology, Delhi, India
2Bhabha Atomic Research Centre (BARC), Mumbai, India
Corresponding Author: S. Roy, roys4095@gmail.com
Utilization of noninvasive radiation based techniques has become widespread in several
industrial applications. Of particular importance is its deployment in systems involving
two or more phases. Such systems are ubiquitously found in areas concerning from the
processing of fuels and chemicals to the production of feed, food, pharmaceuticals, and
specialty materials. In spite of extensive presence of multiphase systems, lack of knowledge
on complex local flow structure have rendered non-availability of any single established
methodology for their design. Nonetheless, two classes of radiation based measurements—
tomographic and velocimetry (commonly referred to radioactive particle tracking)—have
emerged as attractive strategies for providing dynamic information on phase distribution
and flow pattern of phases of interest respectively.
In this work application of such measurement techniques are being reported for fluidization
of coal and bottom ashmixtures. The talk will present details of this work and how radiation
based noninvasive tool proves to be a great benefit in fundamental analysis, design and
scale-up of coal fluidized bed gasifiers.
234 IAEA–CN–241–411
B07
Khane Talk: Session B07, Tuesday 17:45 B07-06
Experimental Study of Pebble Flow Dynamics in a PBMR Using
RPT
V. Khane1, I. A. Said1, and M. Al-Dahhan1
1Department of Chemical & Biochemical Engineering, Missouri University of Science & Technology, Rolla, MO
65409, USA
Corresponding Author: V. Khane, vaibhavkhane@gmail.com
The pebble bed modular reactor (PBMR) is a type of 4th generation nuclear reactor. In a
pebble bed reactor, nuclear fuel is in the form of spherical pebble and moves slowly inside
the core of the reactor under the influence of gravity. A coolant gas moves through the voids
formed in between the pebbles and removes fission heat generated from the nuclear fuel.
Multiphase Reactors and Applications Laboratory (mREAL) at Missouri S&T has designed,
developed, and tested a scaled down continuous pebble re-circulation experimental set-up,
mimicking the flow of pebbles in a PBMR. An experimental study of pebble flow dynamics
in a cold flow setup was carried out using a radioactive particle tracking (RPT) technique
that used a 60Co based tracer to mimic pebbles regarding shape, size, and density in a
noninvasive way. The RPT technique is capable of providing a full description of the 3D
flow field in highly dense and opaque reactors. Obtained results of the radioactive particle
tracking technique regarding Lagrangian trajectories, residence time distributions, velocity
field, etc., are a valuable benchmark data for an assessment of the contact force model used
in the discrete element method (DEM) based simulations.
IAEA–CN–241–023 235
B07
ICARST–2017
B08: Seeing the Invisible: Structure Imaging—Safe
and Effective Industry I
236
B08
Cutmore Talk: Session B08, Wednesday 09:00 B08-01
Next-Generation Fast-Neutron/X-Ray Scanner for Air Cargo
Interrogation
N. G. Cutmore1, J. Tickner1, J. Eberhardt1, R. Preston1, J. Li2, Y. Li2, Y. Liu1, and C. Zong2
1Commonwealth Scientific and Industrial Research Organisation (CSIRO), Australia
2Nuctech Co. Ltd., Haidian District, Beijing, People’s Republic of China
Corresponding Author: N. G. Cutmore, nick.cutmore@csiro.au
There is a growing need for improved methods for rapidly inspecting bulk air cargo, the ma-
jority of which is currently subjected to no physical inspection or scanning. Fast-neutron/X-
ray radiography provides a method to produce images that show the shape, density and
composition of objects in cargo. These can be used to identify a wide range of threat ma-
terials, including organic substances such as explosives and narcotics that can be hard to
resolve using conventional, X-ray–only scanning technology.
Following initial development and demonstration by CSIRO of a fast-neutron/X-ray scanner
at Brisbane Airport in Australia, the technology was commercialized with the Chinese secu-
rity technology firm Nuctech Company Ltd. First-generation air cargo scanners combining
neutron and dual-energy X-ray imaging are operating at airports in the Middle East and
China.
In this paper, we present the latest technical developments, which have focussed on reducing
the footprint, cost and complexity of the technology, whilst improving image quality and
performance. We have developed a completely new plastic-scintillator neutron detection
system with silicon photomultiplier (SiPM) readout. The low-noise characteristics of SiPMs
allow much lower energy neutron interactions to be detected than was possible using our
previous photo-diode based readout, increasing detection efficiency for 14 MeV to 30%.
The small form-factor and simple signal amplification and processing requirements allow
detectors to be tightly packed; the complete detection system includes 1440 elements and has
a five-times higher detection efficiency than the array used in the first-generation scanner.
This efficiency has allowed us to significantly decrease the size of the neutron source. The
first-generation scanner used a liquid-cooled, deuterium-tritium (DT) neutron generator
producing 5ˆ 109 n/s to image air-cargo at scan speeds of up to 6 m/s. The latest system
uses an air-cooled, laboratory-scale neutron generator with an output of just 3ˆ 108 n/s.
With advanced image processing, image quality and scan speeds can be maintained despite
the reduced neutron output. The smaller generator is also considerably easier to install and
maintain in airport environments. We also report on the development of novel, low-cost and
compact neutron shielding, that allows a combined neutron/X-ray scanner to be deployed
within a footprint similar to that of conventional X-ray–only cargo screening systems. Details
of the system and its operation will be presented.
IAEA–CN–241–128 237
B08
B08-02 Talk: Session B08, Wednesday 09:20 Ben Abdelouahed
Monte Carlo Simulation and Experimental Verification of
Blockages in Pipelines Using γ-Ray Computed Tomography
H. Ben Abdelouahed1, J. Abdullah2
1National Center for Nuclear Sciences and Technologies (CNSTN), Sidi Thabet, Tunisia
2Malaysian Nuclear Agency, Bangi, 43000 Kajang, Selangor, Malaysia
Corresponding Author: H. Ben Abdelouahed, haifa.abdelwahed@cnstn.rnrt.tn
Blockages and material build-up in pipelines are a most common problem in many types
of process industries, particularly, in petroleum and chemical industries. Partial blockages
may impair process plant operation whereas total blockages could lead to a shutdown.
Thus, development of non-destructive methods for on-line blockage detection in pipelines
is of a prime importance. In this paper, a study on Monte Carlo simulation using Geant4
code package and an experimental work using a newly developed portable γ-ray computed
tomography (CT) system, called “GammaSpider” for detecting blockages in pipeline was
conducted.
The Geant4 code package provided various features suitable for simulating the geometry
and required parameters of GammaSpider, the results were compared and validated by the
experimental data and finally mass attenuation map of various materials was reconstructed
in 2D or 3D image. Elements to be implemented in the simulation code include a highly
collimated incident beam of 662 keV γ-rays from a 137Cs radioisotope source, the transmitted
radiation after traversing through a cross-section of a 200 mmdiameter steel pipe containing
process water and a simulated partial blockage (concrete deposit) and the transmitted
intensity data were recorded by a collimated sodium iodide (NaI) scintillation detector at
many different translation steps (projections) and rotation angles (views). The results of the
Geant4 simulation permit optimizing the experimental parameters of the γ-ray CT system.
This will also provide an improvement in the resolution of the reconstructed tomographic
images. Results from the Geant4 simulation can be used in planning a test for the routine
use of the GammaSpider system.
238 IAEA–CN–241–149
B08
Zhao Talk: Session B08, Wednesday 09:40 B08-03
Associated Image Processing Algorithm in Dual-Projection
Systems
X. Zhao1, P. Cong1, L. Li1, X. Xiang1, and Y. Zhang1
1Institute of Nuclear and New Energy Technology, Tsinghua University, Haidian, Beijing, People’s Republic of
China
Corresponding Author: X. Zhao, zhaoxi0326happy@163.com
Methods like single-projection detecting and CT detecting are widely used in radiation
scanning systems, however, thesemethods have shortages such as an inability to differentiate
materials and low efficiency so that methods with high accuracy and efficiency are required.
In this paper, we introduce a dual-projection radiation detection technique. Two groups
of radioactive sources and detectors are fixed to obtain gray-scale images of target objects
from two orientations. Algorithms are developed to combine these images and calculate the
shape, position, attenuation coefficient and density of target objects rapidly and accurately.
Ideally, target objects are assumed as convex polygons of single material. The gray-scale
curves follow the ray attenuation theorem which contains physical property information
such as attenuation coefficient and density. Inflections on the curve show when vertexes on
target objects are scanned. To recover the target object geometry from gray-scale images,
algorithms are developed with functions as follows:
1. Locating the position of each inflection on the curves and calculating their coordinates
in real space coordinate where the vertexes are.
2. Combining these calculated vertexes to form polygons and remove those that do not
meet the mentioned assumptions.
3. The selected polygons are re-projected by emulation. The calculated polygon whose
gray-scale curves are closest to the ones of target object is chosen as the result of
recovering. And its position, shape and density can also be calculated.
Matlab simulations were performed, verifying the feasibility of the algorithms. Given
10 mm detectors and an arbitrary pentagon target object, the result shows that the relative
error of calculated absorption coefficient is 0.33%.
Realistic experiments with ideal target were performed. Standard aluminium blocks with
sections of quadrilateral and pentagon are used as the target. The detectors are 7 mm in size
and the radioactive source is 60Co. The relative error of calculated density is within 3–5%.
The difference between two experiment results of absorption coefficient is 4ˆ 10´3 which
shows the high reproducibility of this system. Further experiments using non-ideal objects
were made. A bucket of water was put in a container as the target. By moving the container
continuously, a series of gray-scale curves, representing different sections of all things in
it, are obtained and processed to recover the shape and position. The results show that
the relative error of calculated density is 10.4% after eliminating the impact of background
noise.
Details of the method and its application will be presented.
IAEA–CN–241–383 Presenter: P. Cong 239
B08
B08-04 Talk: Session B08, Wednesday 10:00 Myaing
Comparison of Image Reconstructions for γ-Transmission
Computed Tomography System by Using MATLAB and i-Gorbit
Software
K. N. Myaing1
1U Chit Khe, Myanmar
Corresponding Author: K. N. Myaing, khaing.nm@gmail.com
With wide industrial application, computerized tomography (CT) is a rapidly developing
technique that is especially useful for imaging and measuring multicomponent and multi-
phase processes. The most important contribution of CT is to greatly improve abilities to
distinguish regions with different γ-ray transmittance and to separate over-lying structures.
The CT system of single source and detector γ-transmission tomography GORBIT, designed
by CANTI, Viet Nam, was used to analyze different density materials. Hardware of the
GORBIT CT system consists of two servo motors, data logger, computer, a radiation source
and a radiation detector. The measurements in GORBIT system were carried out at the CT
Laboratory in the Department of Atomic Energy, Yangon. This tomography system operates
with a γ-ray source of 60Co at 1.85 GBq (50 mCi) and a NaI(Tl) scintillation detector.
Measured γ-transmission data were used to reconstruct the cross-sectional images of re-
search samples. These images were reconstructed from the measured data via different
image reconstruction algorithms. Analytical methods of back projection (BP), the filtered
back projection method (FBP) and iterative algorithms of algebraic reconstruction method
(ART) and estimation maximizations (EM) methods were used in i-GORBIT image recon-
struction software. Another image reconstruction programme GCTS was created by using
MATLAB package. In this image reconstruction, different algorithms of back projection (BP)
and filtered back projection (FBP) were used. In FBP method, different filters of Ram-lack
filter, Sheep-Logan, Hamming, Hann and Cosine filter can be chosen and different interpo-
lation methods can be applied to improve the image quality. The results of different image
reconstruction programmes were compared and analyzed for the sample materials. In this
research work we will present some results obtained by using tomographic techniques
to analyze various samples to check the distribution of various density materials. These
samples are made by using different properties of materials with high and low density
materials of lead, iron, six-hole bricks, polymer slab contained in a polymer pipe vessel.
These samples are also used to verify the outcome from the CT analysis with different image
reconstructions programmes i-GORBIT and MATLAB.
240 IAEA–CN–241–283
B08
Dang Nguyen Talk: Session B08, Wednesday 10:20 B08-05
Gorbit – The Flexible γ-Computed Tomography System for
Pipeline Inspection
T. D. Dang Nguyen1, D. Pham Van1, D. Bui Trong1, and Q. Nguyen Huu1
1Centre for Applications of Nuclear Technique in Industry (CANTI), Dalat City, Lamdong Province, Viet Nam
Corresponding Author: T. D. Dang Nguyen, theduy@canti.vn
γ-computed tomography is a non-intrusive technique, capable of providing density-based
images of structure or phase distribution inside industrial components without shutting
down or disturbing normal operation. However, the field applications pose many challenges
to a tomography system related to mobility, compatibility to mount on the components,
weight and cost of system, etc. Enter GORBIT, a flexible γ-computed tomography system
designed and fabricated for pipeline inspection. The first version of GORBIT was based
on the parallel configuration that allows inspection of pipelines of OD up to 600 mm at
any angle, easy installation and mounting on the pipe and automatic scanning. The image
resolution can be achieved 16 ˆ 16, 32 ˆ 32, 64 ˆ 64, 128 ˆ 128 and 254 ˆ 254 pixels.
The image reconstruction software was also developed based on filter back projection
(FBP) and algebraic reconstruction technique (ART) algorithms. The GORBIT system has
been deployed to inspect pipelines in the petroleum industry for detection of corrosion,
deformation and blockage. GORBIT was also used for in-house experiments to validate the
CFD simulation results of fractional phase flows.
The new version of GORBIT was recently developed based on the modified 3rd generation
using fan beam that reduced significant operation time while maintaining the resolution of
the image.
IAEA–CN–241–118 241
B08
ICARST–2017
B09:Radiotracer for Managing Natural Resources
242
B09
Mimount Talk: Session B09, Wednesday 11:15 B09-01
Development of Radiometric Methods for Optimization of
Phosphate Transport Process by “Slurry Pipe”
S. Mimount1, O. K. Hakam2, A. Saadaoui1, and K. El Korchi1
1Centre National de l’Energie des Sciences et des Techniques Nucléaires (CNESTEN), Rabat, Morocco
2University of Ibn Tofail, Kenitra, Morocco
Corresponding Author: S. Mimount, samira.mimount@gmail.com
Moroccan reserves of phosphates are the largest in the world, estimated to be more than
85 billion m3. The drainage of the phosphate rock from the mine site to the chemical
sites, which is currently done by train, requires dry phosphate to lower the humidity in
order to carry it cheaply. However, the chemical processing of raw phosphates, to get
the final products (phosphoric acid, fertilizers, etc.) requires large amounts of water to
be reintroduced. For the transport of phosphate, it has been decided to build a pipeline
between Khouribga mines to the JorfLasfar chemical units, to help converge the problems
of transport cost reduction and rationalization of water and energy consumption.
Determination of physical parameters, such as concentration, viscosity, flow rate, etc., of the
material inside the pipe becomes a key issue for handling andmaintaining the whole system.
The current study aims to develop radiotracer methodologies and specific nucleonic control
systems to obtain such information. The first phase of the study consists in carrying out of
a series of field experiments, targeting flow measurement of pulp phosphates transported
by gravity, by using radiotracers (131I) in various flow conditions.
IAEA–CN–241–297 243
B09
B09-02 Talk: Session B09, Wednesday 11:30 Diaz
Determination of Mineral Behaviour in Ball Mills at Chilean
Copper Minning Using Radioactive Tracers
F. Diaz1, O. Jimenez1, F. Contreras2, and L. Vinnett3
1Trazado Nuclear, Santiago, Chile
2Los Pelambres mine, Salamanca, Illapel, Región de Coquimbo, Chile
3Automation and Monitoring Center for the Mining Industry (CASIM), penalty -1 Department of Chemical and
Environmental Eng., Federico Santa Maria Technical University, Valparaíso, Chile
Corresponding Author: F. Diaz, fdiaz@trazadonuclear.cl
Minera Los Pelambres (MLP) is located in the IV Region of Chile, with a mine located at
3100 m a.s.l and a concentrator located at 1600 m a.s.l. MLP started its operation in the
year 2000 and by 2015 it was one of the 10 largest producers of copper concentrate in the
world, achieving 405 300 tons of copper and 9000 tons of molybdenum concentrates in
2013. MLP has established within its goals to improve the process efficiency and to increase
the concentrate production. For these reasons, all the process stages are being evaluated,
including the comminution circuits (crushing and grinding), which are the most intensive
in terms of energy consumption.
The MLP grinding circuit consists of three parallel SAG mill lines, each one formed by a
semi-autogenousmill (SAG) and two parallel ball mills. The first two SAGmill lines have ball
mills of 10 500 HP, and the third has one ball mills of 10 500 HP and another of 20 700 HP.
The ball mills operate in a closed-circuit (direct circuit) with a hydro cyclone battery, which
allows adequate particles for the flotation process to be obtained. In this paper the fluid
dynamic characterization of ball mills by means of the residence time distribution (RTD)
is presented. The RTD were obtained at industrial scale by using direct measurements of
radioactive tracers in the input and output streams of the ball mills.
Dried mineral samples from the hydro cyclone underflow were used as a solid tracer. This
material was irradiated by neutron activation in the La Reina Nuclear Center, Chilean
Nuclear Energy Commission. The RTD determination was obtained by measuring the solid
tracer in the input and output streams of the ball mills, employing scintillation detectors
for real-time measurements. The tracer activities were of 15 mCi of 24Na in each injection,
which contained between 15 and 30 g of solid. A pneumatic system was designed for the
tracer injections, which allows the tracer injection to be carried out remotely.
The measurements demonstrated that a significant percentage of tracer recirculation to
the input stream exists. Therefore, the use of parametric deconvolution methods for the
RTD determination were required. The model of N perfectly mixed reactors in series was
employed for the RTD descriptions, where N ranged from 2.1 to 3.9 with effective mean
residence times between 1.9 and 9.5 minutes. The RTD estimation by the use of radioactive
tracers is a powerful tool to characterize the mixing regime in large industrial machines
from the mining processes and other productive industries.
244 IAEA–CN–241–113
B09
Rogowski Talk: Session B09, Wednesday 11:45 B09-03
Radiotracer Methods for Ore and Flotation Tailings Leaching
M. Rogowski1, T. Smolinski1
1Institute of Nuclear Chemistry and Technology (INCT), Warsaw, Poland
Corresponding Author: M. Rogowski, m.rogowski@ichtj.waw.pl
Copper mining and ore processing is one of the most stable and profitable branches of the
Polish economy and its fastest growing industry. However, the technologies used lead to
high losses of valuable and so-called deficit metals (rare earths, uranium and copper) in solid
wastes streams. The development and implementation of hydrometallurgical technologies
is a feasible solution for efficient higher element recovery and decreased toxicity of the
wastes storage on the environment. Radiotracer methods are the suitable tool for process
investigation since most of the elements involved may be activated and their radioactive
isotopes easily detected. The separation efficiency, process kinetics and flow dynamics of
hydrometallurgical systems can be therefore qualitatively and quantitatively evaluated.
The objective of the project is the elaboration of a new efficient method to recover copper and
critical metals from the various raw materials using radiotracers for process optimization.
A key stage of themetal recovery process is a leaching process. The rawmaterial was crushed
and decarbonized using oxidation techniques and characterized. Initial concentrations of
copper and other elements were determined by ICP-MS, ASS and chromatography methods.
The leaching process is carried out in a periodic chemical reactor. For process optimization,
a radiotracer techniques based on nuclear activation analysis has been used. The samples of
the material were activated by a neutron flux at the MARIA Reactor and mixed with leached
materials. The radiotracers (activated 64Cu) were used to determine leaching efficiency
instead of common analytical methods. The results were validated using ICP-MS and ASS
analyses. Obtained metal solution will be separated at mixer settlers and ion exchangers
also optimized by radiotracers techniques.
As raw material we used copper ore and flotation tailings. As we expected, the samples
contain several metals (Cu, V, Zn, Co, Ag, Ni, Mo, Fe, Pb, Mn, U, REE, etc.). The copper
concentration was at 4% in the ore and less than 1% in the tailings waste. Sulfuric acid
was selected as the optimal leaching medium for future experiments. The material was
ground and sieved to extract individual fractions. The optimal granulation was selected:
0.25–0.5 mm. At the leaching step the material was treated with sulfuric acid at various
concentrations (2–16 M). We also calculated activation parameters for developing activation
procedure. The samples were activated and used at leaching experiment for RTD test.
Radiotracer methods seems to be a suitable tool for leaching process investigation since most
of the elements involvedmay be activated and their radioactive isotopes easily detected. The
separation efficiency, process kinetics or flow dynamics of hydrometallurgical systems can
be therefore qualitatively and quantitatively evaluated. Radiotracer methods were validated
using common analytical procedures and can be used instead of them for controlling and
optimization of the process.
This work is part of the studies for the IAEA Coordinated Research Projects: “Radiomet-
ric Methods Applied in Hydrometallurgical Processes Development and Optimization”
and “Radiometric and Radiotracer Techniques in Hydrometallurgical Processes for Deficit
Elements Recovery” co-financed by the Polish Ministry of Science and Higher Education.
IAEA–CN–241–070 245
B09
B09-04 Talk: Session B09, Wednesday 12:00 Pant
Radiotracer Investigation in an Industrial-Scale Fluid Catalytic
Cracking Unit
H. J. Pant1, P. Brisset2, P. Berne3, G. Gousseau3, and A. Fromentin3
1Bhabha Atomic Research Centre (BARC), Mumbai, India
2International Atomic Energy Agency (IAEA), Vienna, Austria
3DTEN/SAT-CEA Grenoble, Grenoble Cedex, France
Corresponding Author: H. J. Pant, hjpant02@gmail.com
Fluid catalytic cracking (FCC) is one of the main processes used for processing crude oil
in refineries. The cracking process efficiency depends upon process parameters such as
residence time, residence time distribution, radial distribution and axial mixing of catalyst
and gas phases in various sub-units such as riser, disengager, stripper and regenerator of
the FCCU. Radiotracer techniques are widely used for measuring process parameters in
industrial process systems. The measured parameters are often used for troubleshooting,
performance evaluation, design improvements, and process visualization, optimization
and intensification. This paper describes a series of radiotracer experiments carried out
in an industrial-scale FCCU in India to measurement the flow parameters of catalyst and
gas phase in various sub-systems of the FCCU. The objective was to measure the process
parameters to evaluate performance of the FCCU and process intensification.
A series of radiotracer experiments was carried out in four sub-units of the FCCU for tracing
catalyst and gas phases. Lanthanum-140 (140La) as catalyst itself and krypton-79 (79Kr)
gas were used as radiotracers for tracing catalyst and gas phase cracked, respectively. The
amount of activity used for tracing catalyst and gas phase in different sub-systems ranged
around 0.5–2 GBq and 4–8 GBq, respectively. The radiotracer was instantaneously injected
at the inlet of each sub-system and monitored at different strategically selected locations
using scintillation detectors.
The data recorded in different radiotracer tests were treated and analyzed. From the treated
curves mean residence time, velocity and slip factor were obtained. In order to investigate
radial mixing of the phases across the cross-sections of the different sub-systems, multiple
detectors mounted at each axial location were plotted and analyzed. In case of a good radial
distribution, all the detectors mounted at an axial position will provide identical responses
provided the wall and insulation thicknesses at the monitoring conditions were identical.
However, different intensities of the monitored curves will indicate poor radial distribution
of the phases. To investigate axial mixing, and axial dispersionmodel was used and values of
model parameters, i.e., Peclet number (Pe) were obtained. The parameters were successfully
measured and flow anomalies were identified. Homogeneous radial distribution of the
two phases was observed in the riser section of the FCCU, whereas in other sub-systems,
the radial distribution of the phases was poor. The velocity of gas and solid phase were
measured to be 9.9 and 6.4 m/s, respectively. The slip factor was estimated to be 1.5, which
was as per design criteria for efficient cracking reactions in the riser section. The flow of
gas phase in the riser was observed to be as plug flow, however, moderate degree of axial
backmixing was observed in case of catalyst flow. The results obtained helped to plan the
necessary modifications in the FCCU, scale up the capacity and optimize the performance
of the system.
246 IAEA–CN–241–320
B09
Tickner Talk: Session B09, Wednesday 12:15 B09-05
Developing a Commercial Facility for Rapid Assay of Gold and
other Elements in Mineral Ores Using γ-Activation Analysis
J. Tickner1, C. Tissot1, and J. Delaney1,2
1Commonwealth Scientific and Industrial Research Organisation (CSIRO), Australia
2University of Wollongong, Wollongong NSW 2522, Australia
Corresponding Author: J. Tickner, james.tickner@csiro.au
The global mining industry relies on elemental analysis throughout their value chain. The
development of near real-time analysis techniques such as on-stream and hand-held X-ray
fluorescence allows assay data to be used for process control and optimization. Unfortu-
nately, current methods have insufficient sensitivity to measure metals such as gold, which
are mined at concentrations of a few parts-per-million (ppm) or less. Gold is currently mea-
sured commercially using the process of fire-assay, a laborious, time-consuming, manually
intensive and hazardous process. Extensive sample preparation requirements mean that
analysis turn-around times are typically at least 24 hours, precluding the use of the results
for control purposes.
We have been developing γ-activation analysis (GAA) as an alternative approach. GAA
mimics the more conventional neutron activation analysis (NAA), using a high-intensity
radiation source to activate target elements in samples, and then measuring characteristic γ-
rays emitted from activated radioisotopes. Unlike the nuclear reactor commonly required for
NAA however, GAA uses a high-energy X-ray beam produced using an electron accelerator.
GAA is particularlywell-suited to the analysis of gold via excitation of the 409 keV, 7.73 s half-
lifemeta-state of 197Au. The short half-life of themeta-state, and the fact that it can be excited
using X-ray with energies below the activation thresholds of major rock-forming elements,
make the method particularly rapid and sensitive. Notwithstanding these potential benefits,
the GAA method has found only very limited commercial application, with only one
industrial facility operating worldwide to our knowledge.
In this paper we report developments in several areas:
• Our work to better understand the physics of GAA and significantly improve sensitiv-
ity and accuracy. We demonstrate how a novel correction method allows accuracies
of better than 1–3% to be achieved.
• Optimization of a practical system for round-the-clock commercial operations, in-
cluding X-ray source design, shielding, detectors, and automated sample handling.
• Safety and regulatory approval. We discuss the development and use of advanced
Monte Carlo software tools for shielding design and evaluation of residual activity.
• A profitable facility model and effective industry engagement strategy. We detail
experiences setting up our first commercial GAA facility and our strategy for engaging
with industry partners and customers to build acceptance of a new analysis method.
• Planning for a containerized GAA facility, suitable for rapid deployment on mining
and mineral processing sites to facilitate provision of near real-time analysis data.
The new facility is currently in the advanced planning stage and is scheduled to start
operations in mid-2017.
IAEA–CN–241–134 247
B09
B09-06 Talk: Session B09, Wednesday 12:30 Moreira
A Tracer Application in Detecting Damage to Oil Industry Piping
R. M. Moreira1
1Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), CNEN, Brazil
Corresponding Author: R. M. Moreira, rubens@cdtn.br
Damage to the internal surfaces of piping systems of process industries is caused by continu-
ous exposition to mechanical and chemical processes throughout their life span. This paper
reports on a preliminary evaluation as to whether radiotracer techniques can be used in the
detection of the two most frequent deterioration processes in an oil production and refining,
viz., corrosion and scaling. Usually conventional non-destructive tests, all of which suffer
from some limitation, are used in inspecting the impaired material and equipment. In turn,
radiotracers are can be inserted into the flow and afford easy detection and measurement.
The question: Is the method is sensitive enough? Residence time distribution models that
are widely used in fluid flow studies may disclose the conditions inside the investigated
system.
In this paper both the competence of the tracer technique in identifying which process—
corrosion or scale formation— is acting, and of evaluating how much it is interfering with
the flow. The tests were performed in pieces of the API 5L-B structural steel, commonly used
in oil refineries. Three test specimens were used: one was flawless (CP-A), in a second one
(CP-B) an ad hoc groove had been carved around its inside surface aiming at simulating a
corrosion singularity, and in the third one (CP-C) an encircling metallic bulge was welded to
its internal surface to simulate a scaling anomaly. Activatedmanganese sulfate monohydrate
(56MnSO4‚H2O) in aqueous solution was used as the radioactive tracer. The manganese salt
has been irradiated in the CDTN TRIGA reactor facilities. A fluorescent tracer (Rhodamine-
WT) has also been tested for comparative purposes. The testswere performed under different
flowrate conditions: 0.10, 0.40, and 0.90 m3{h. The DTSPRO software has been used to
analyze the flow residence time distribution curves and the ANSYS CFX 15 fluid dynamics
software was used to define the flow in the flow obtained inside test specimens. The results
achieved with both radioactive and fluorescent tracers indicated that the presence of the
discontinuities in the specimens caused a perturbation in the flow that could be detected by
the tracer technique. No deviations relative to a free flow were found in the CP-A probe,
whereas some localized recirculation was detected in the CP-B probe, and stagnation or
dead zones were noticed in the CP-C probe. It has been considered that the tracer technique
has a potential use in discerning the presence of discontinuities such as corrosion and scale
formation in pipes.
248 IAEA–CN–241–441
B09
ICARST–2017
B10:Radiotracers for NewMaterials Development
249
B10
B10-01 Talk: Session B10, Wednesday 16:30 Makil
Quality Control of Neutron-Absorber Materials for the Nuclear
Fuel Cycle: Principle of the JEN_3 Neutron Backscattering Gauge
H. Makil1, P. Brisset2
1Commissariat à l’énergie atomique (CEA), France
2International Atomic Energy Agency (IAEA), Vienna, Austria
Corresponding Author: H. Makil, hamid.makil@cea.fr
It is projected that by 2030 there will be other nuclear reactors in addition to 437 reactors
already operating commercially today in the world. A quarter to the third of the spent fuel
rods from these reactors must be removed from a reactor every 12 to 24 months and stored
between one and two years in the spent fuel pools. This delay allows the decrease of their
radioactivity and thus their cooling, in order to facilitate transportation to the reprocessing
plant. During that pool storage period, prevention of critically is ensured by the borated
stainless steel plates, used as coated of the spent fuel pools. In general, this material plays a
major role in the nuclear fuel reprocessing industry as a neutron-absorber material.
Several metallurgy techniques have been developed for manufacturing the borated stainless
steel plates. To ensure a functional of radiation protecting and criticality, this material must
meet strict specifications regarding the boron content and uniform distribution of the boron
in the stainless steel plate. CEA (French Atomic Energy Commission) has designed several
gauges to provide proof through non-destructive inspection that the finished products fully
satisfy their intended objectives.
The main geometries have been considered:
• Backscattering geometry, when the criticality shield must reduce the reflection of
neutrons.
• Transmission geometry, when the shield must reduce the interaction of exchanging
neutrons.
In this paper, we present the JEN-3 Backscattering neutron gauge. This gauge contains a
neutron radio-isotopic sealed source whose activity depends in the final control and the site
constraints. The neutron measurement is affected by randomness of the neutron emission
and their interactions with the matter so, the uniform distribution of the boron will be
checked by statistical criteria of acceptability.
The industrial prototypes are already installed and their performances have been validated
in two manufactures of borated stainless steel plates (the first one in Austria and the second
one in the US).
250 IAEA–CN–241–436
B10
Kleinrahm Talk: Session B10, Wednesday 16:50 B10-02
Radionuclide Technique in Mechanical Engineering: A Powerful
Measuring Method for Tribological Tasks — Installations at and
Services of ZAG Zyklotron AG
A. Kleinrahm1
1ZAG Zyklotron AG, 76344 Eggenstein-Leopoldshafen, Germany
Corresponding Author: A. Kleinrahm, achim.kleinrahm@zyklotron-ag.de
The radionuclide technique in mechanical engineering RTM is a powerful and sensitive
method to measure online the wear rates of running engines or tribometers in the range of
nm/h. The three parts of this technique will be explained: 1) The process of radioactive
labelling at a cyclotron; 2) The two possible measurement procedures; and 3) The measure-
ment equipment. The installations for machine part activations at the cyclotrons of ZAG
Zyklotron AG are shown. Based on measurement examples, the possible sensitivity of this
method is demonstrated. Special developed activations and the status of implantations of
radioactive ions are discussed.
IAEA–CN–241–040 251
B10
B10-03 Talk: Session B10, Wednesday 17:10 Artemiev
Replacing the Isotopic Radiation Sources in Thickness
Measurement on X-Ray
B. Artemiev1, I. Artemyev1
1ZAO “RII-MSIA” “Spectrum”, 119048, Moscow, Russian Federation
Corresponding Author: B. Artemiev, boris@artemiev.su
Currently, there is a tendency in industry if refusing isotopic radiation sources in favour
of X-ray machines. This is due to several factors, chief among them radiation safety and
maintenance problems, movement and disposal of γ-ray sources.
Compared to the γ-ray source devices have a number of disadvantages. The spectral energy
distribution and therefore change in the spectrum as the radiation passes through the
controlled material. Instability of radiation compared with γ-sources. All this complicates
the use of X-ray sources for the thickness measurement of materials with different chemical
compositions.
We offer solutions that reduce the measurement error when using X-ray radiation sources
below 0.2% of the measured value.
252 IAEA–CN–241–135
B10
Ditrói Talk: Session B10, Wednesday 17:30 B10-04
Development of Thin Layer Activation for Wear Measurement
F. Ditrói1, S. Takács1
1Institute for Nuclear Research, Hungarian Academy of Sciences, Debrecen, Hungary
Corresponding Author: F. Ditrói, ditroi@atomki.hu
Since the early 80s, when a cyclotron was installed in our laboratory, both fundamental re-
search and application areas have been established. In the first years of operation, a relatively
large amount of radioactive isotopes was produced for medical purposes. Parallel with the
medical isotope production, a number of other isotopes were elaborated for industrial and
agricultural purposes, intended for use as radioactive tracers. During the cooperation of
national and foreign companies and research institutions the idea of using the radioactive
tracers for wear, corrosion and erosion measurements emerged. Appropriate irradiation fa-
cilities were elaborated for activation of different parts of different forms and sizes as well as
simple pieces of equipment (grinding machine, Microtom, etching desk, etc.) were installed
to monitor the wear of the activated parts. During the cooperation, real machine parts
were activated and investigated in tribometers or test benches. By broadening the range of
the materials and samples to be investigated it turned out that the nuclear data, especially
the cross-section and yield data for nuclear reactions necessary to estimate the produced
activities are poor in some cases, that’s why we launched a nuclear data measurement and
compilation programme to establish a database for these reactions in cooperation with the
IAEA. The materials, which cannot be activated directly were labelled using the secondary
recoil activation. The international transport regulations and cooperation partners without
licence for using radioactive materials in their premises motivated us to elaborate the thin
layer activation (TLA) method by using activities under the free handling limit (FHL).
The irradiations/activations are performed on a dedicated beam line of our cyclotron
laboratory mainly with proton or deuteron activation. The bombarding energy is set to a
value so that the activity distribution of the main radioisotope produced is constant up to a
given depth of the surface (homogeneous activation). If it is not possible the distribution is
set to linear. Single or multiple spots, larger areas are activated into a depth required by the
particular task. The depth can be adjusted by altering the irradiation angle. A particular task
may require the presence of different radioisotopes in the same sample or in two samples
with friction contact. In this case a non-interfering pair of isotopes are chosen. The first
measurements are performed by using high resolution γ-spectrometers in order to assess
all isotopes and their activities, the real wear (corrosion or erosion) measurement can be
performed by high efficiency detectors (e.g., scintillation crystal) with discrimination to a
given radiation of the chosen isotope.
During more than 20 years experience in thin layer activation we could successfully use
both the high activity method and the FHL activations to solve real wear measurement
tasks, as well as developed the production of a series of radioisotopes applicable for wear
measurements. Our results also extend to the nuclear data measurements, where much
more radioisotopes are measured and discussed from the point of view of TLA.
IAEA–CN–241–042 253
B10
B10-05 Talk: Session B10, Wednesday 17:50 Genezini
Industrial Applications of the IEA-R1 Research Reactor in Brazil
F. Genezini1,W. A. P. Calvo1, A. J. Fernando1, A. Marra Neto1, and P. E. Aoki1
1Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), São Paulo, Brazil
Corresponding Author: F. Genezini, fredzini@ipen.br
The IEA-R1 is an open pool type research reactor located at the Nuclear and Energy Research
Institute (IPEN-CNEN/SP) site and achieved its first criticality on September 16, 1957.
IEA-R1 is the largest research reactor in operation in Brazil, with a core composed of
24 fuel elements with 20% enriched uranium silicide, 4 control rods (Ag`In`Cd) and many
irradiation positions supplying thermal neutron fluxes ranging from 1012 to 1014 n/cm2s.
Currently, IEA-R1 is operating at 4.5 MW on an 8 hours per day and 4 days per week cycle.
The IEA-R1 reactor is a multipurpose facility used for basic and applied research in nuclear
and for the production of radioisotopes for industry and nuclear medicine. For industry,
IEA-R1 produces radiotracers and sealed radioactive sources (60Co and 192Ir) for industrial
γ-radiography, as well as doped silicon by neutron transmutation.
For radiotracer production, IEA-R1 has been working with a compact local staff (3 persons)
and is assisted by the Radiation Technology Centre at IPEN-CNEN/SP, in which there are
installed hot cells for high activity handling. Most of the radiotracers produced at IEA-R1
are irradiated in a quartz bulb inside an aluminium vessel; the only exception is for 41Ar
production, where a special device that doesn’t require a hot cell is used. These are the
radiotracers produced at IEA-R1 and their applications in industry and environment:
• 203Hg: determination of the mercury mass immobilized in electrolytic cells from soda
and chlorine producing industries (46.6 days and 0.28 MeV).
• 131I and 82Br: flow rate measurement and residence time distribution (RTD) studies
in rivers, lakes and wastewater treatment plants (8.04 days and 36 h, 0.36 MeV and
0.55 MeV, respectively).
• 192Ir: environmental studies, in the form of a premixed sand (glass powder plus
activated iridium), to study drag sediment in river (73.8 days and 0.32 MeV).
• 198Au: representative study, in real conditions, of the impact of great civil works for
the construction of important artificial harbour, airport and hydroelectric reservoir,
by labelling sand to be removed from the bottom with emulsion of gold (2.7 days and
0.41 MeV).
• 41Ar and 79Kr: study the gas phase of fluidized cracking catalytic plants (110 min
and 35 h, 1.29 MeV and 0.51 MeV, respectively).
• 140La: study the solid phase (catalysts) of fluidized cracking catalytic plants in
petroleum refineries (40 h, 1.16 MeV).
For doped silicon production, a device that affords the best axial and radial uniformity of
the neutron dose is used. These doping uniformities as well as the doping accuracy are
determined using resistivity values, showing an excellent doping quality.
A recent improvement was the development of an irradiation system to produce gaseous
radioisotopes (41Ar and 79Kr), delivering the activated gases directly into the shield bottle
without handling and dose exposition for operators, instead of via small quantities (batches),
through quartz ampoules containing these noble gases.
254 Presenter: W. A. P. Calvo IAEA–CN–241–455
B10
ICARST–2017
B11: Seeing the Invisible: Structure Imaging—Safe
and Effective Industry II
255
B11
B11-01 Talk: Session B11, Thursday 09:00 Ud Din
Investigation of Two-Phase Flow Behaviour Across a 90 Degree
Horizontal Bend: CFD Simulation and γ-Computer Tomography
Validation
G. Ud Din1, S. Gul1, M. B. U. Zaman1, and I. H. Khan1
1Pakistan Institute of Nuclear Science and Technology (PINSTECH), Nilore, Pakistan
Corresponding Author: G. Ud Din, ghiyasuddin@hotmail.com
Investigation of two-phase (gas-liquid) flows is of vital importance due to their numerous
applications in process industry. In the era of high speed and high capacity computers, such
process engineering investigations are carried out using computational fluid dynamics (CFD)
simulations. However, there is always a need to validate the fascinating CFD simulation
results with experimental technique. γ-computer tomography (CT) provides a means to
validate CFD results. In this technique, the transmission property of γ-rays is used to
exploit density distribution of materials in the process under investigation. This procedure
is carried out by obtaining several radiographic projections of the process followed by image
reconstruction using various image reconstruction algorithms.
Two-phase flow regimes in straight pipes are well established and reported in literature but
little has been focussed to define these flow regimes across bends. This paper presents an
investigation of two-phase (air-water) flow behaviour across a 90 degree horizontal bend
for a range of superficial velocities of phases using CFD and γ-CT techniques. Simulation
of the system is carried out using the software FLUENT 6.3.26 while computational grid
was generated using the preprocessor GAMBIT 2.4.6. Euler-Euler multiphase model is
used while turbulence is incorporated using the standard k-epsilon model. Validation
of simulation results is carried out using the first generation γ-CT system GORBIT. The
90 degree horizontal bend is scanned at various cross-sections for this purpose. Stratified
flow patterns with major portion of void at the upper section of bend have been observed
on the inlet and outlet of bend on the studied operating parameters. However, the void has
been noticed to move towards the inner curvature of bend at the central location.
256 IAEA–CN–241–356
B11
Jin Talk: Session B11, Thursday 09:15 B11-02
New Developments on the Automatic γ-Column Scanner
J.-H. Jin1, S.-H. Jung2, J.-H. Moon2, and J.-G. Park2
1GammaTech Inc., Republic of Korea
2Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
Corresponding Author: J.-H. Jin, joonha.jin@gmail.com
Gamma transmission scanning of distillation columns is one of the most frequently used
radioisotope techniques in industry. Recently, a new version of an automatic γ-column
scanner was developed by cooperation between KAERI and GammaTech Inc., to facilitate
high quality γ-scanning services to local industry. The scanner controls the movements of
the source and the detector, records radiation counts and shows graphically the result of
scanning on the screen. Instead of using multiple lines (guide cables, holding cable, signal
cable and ruler) for the source and the detector in manual column scanning system, only
one line is used in each side by employing tensioning tools and wire signal cable in the
automatic system. Remarkable improvement in both hardware and software were made in
the new version. The new system features shockless movement of a source and a detector
for their precise control which is pivotal for acquiring measurements with high confidence.
Software and associated hardware of the system was built with the products that have a
worldwide reputation as standard tools in engineering fields to make the maintenance as
well as further improvement more convenient. The improvements in the tensioner system,
the encoder and its calibration method, radiation detection system and γ-energy spectrum,
control box, software programme and its operationmethods are introduced. The procedures
for installation and operation of the scanner are presented.
IAEA–CN–241–311 257
B11
B11-03 Talk: Session B11, Thursday 09:30 Pant
Radiotracer Applications in Industry and Environment
H. J. Pant1
1Bhabha Atomic Research Centre (BARC), Mumbai, India
Corresponding Author: H. J. Pant, hjpant02@gmail.com
Radiotracer techniques are widely used for troubleshooting, measurement of hydrodynamic
parameters, flow visualization and evaluation of design of process equipment in industry
and environment because of their many advantages over conventional tracers. The main
advantages of radiotracers are their physico-chemical compatibility, high detection sensi-
tivity, ability of in situ detection, availability of a wide range of radiotracers for different
phases, non-degradability in harsh industrial environment and limited memory effects. In a
radiotracer application, the radioactive material in a suitable physo-chemical form, similar
to that of the process material, is instantaneously injected into the system at the inlet and
its passage is monitored at the outlet or along the system at strategically selected locations
using collimated radiation detectors. The monitored tracer concentration data is plotted as
a function of time and interpreted to obtain qualitative as well as quantitative information
about process parameters, hydrodynamic behaviour of the system and occurrence of mal-
functions, if any. The commonly carried out applications of radiotracers in industry and
environment across the world include:
• Leak detection in buried pipeline and heat exchangers;
• Mixing/blending studies;
• Flow rate measurements;
• Studies on residence time distribution in process vessels;
• Sediment transport investigations in port;
• Effluent dispersion studies in water bodies;
• Wear rate measurements;
• Radioactive particle tracking technique for flow characterization;
• Radiotracer applications in oil field investigations.
These applications across the world are either carried out by private companies or atomic
energy establishments of the different countries. The end-user industries have been enor-
mously benefited from these applications. In recent years, some new developments have
also taken place in tracer techniques. During the presentation, a few case studies recently
conducted in India and emerging trends in radiotracer applications in industry and envi-
ronment will be discussed.
258 IAEA–CN–241–319
B11
Johansen Talk: Session B11, Thursday 09:45 B11-04
Tomographic Methods for Multiphase Flow Measurement
G. A. Johansen1, C. Sætre1, T. Stein-Arild1, and H. Bjørn Tore1
1University of Bergen, 5007 Bergen, Norway
Corresponding Author: G. A. Johansen, geir.johansen@ift.uib.no
Measurement of multiphase flow of gas, oil and water is not at all trivial and in spite
of considerable achievements over the past two decades, important challenges remain.
These are related to reducing measurement uncertainties arising from variations in the flow
regime and the fluid properties, improving long term stability and developing new means
for calibration, adjustment and verification of the multiphase flow meters.
Tomographic imaging is a powerful tool to unravel the dynamics of the gas liquid distri-
bution in multiphase pipe flow and is regularly applied to provide reference data in the
development of multiphase flow meters and for experimental validation and development
of flow models. A high-speed γ-ray tomograph developed at the University of Bergen
has been developed for this purpose. The image capture rate in the example shown is
100 frames/second, however, the system is capable of identifying the gas-liquid distribution
at rates up to 1000 frames/second.
The high-speed imaging systems are designed for use in laboratories and at test facilities
and are not suitable for in situ or permanent installations. For this purpose simpler systems
with fewer projections are applied. These are referred to as tomographic measurements,
tomometry or agile.
An example of a γ-ray system using one source and multiple beams, will be presented.
This concept can be applied as a stand-alone meter or to provide accurate measurements of
the gas volume fraction for a multiphase flow meter. The pipe flow is split into temporal
segments of which the gas volume fraction is measured. One 241Am source with principal
emission at 59.5 keV is used because this relatively low energy enables efficient collimation
and thereby shaping of the beams, as well as compact detectors. One detector is placed
diametrically opposite the sourcewhereas the second and eventually the third are positioned
to the sides so that these beams are close to the pipe wall. The principle is then straight
forward to compare the measured intensities of these detectors and through that identify
the instantaneous cross sectional gas-liquid distribution, i.e., the instantaneous flow pattern.
By counting the intensity in short time slots (ă 100 ms), rapid variations are revealed.
In conclusion the sensitivity to temporal flow regime variations multiple beams are con-
siderably reduced by this multiple beam principle and is now implemented in commercial
meters.
IAEA–CN–241–350 259
B11
B11-05 Talk: Session B11, Thursday 10:00 Maghella
Determination of Interfaces in Packed Columns by Using Sealed
Sources
G. Maghella1, J. Maguiña Leon1
1Instituto Peruano de Energía Nuclear, Lima, Peru
Corresponding Author: G. Maghella, gmaghella@ipen.gob.pe
Process involved is the application of nuclear gauges to evaluate bed interfaces in packed
columns, which are used in different industries, petrochemicals, etc. In this case, different
types of packing have been used within a PVC column in order to analyze the γ-radiation
attenuation response that different materials, of different density, present when a radioactive
source whose beam passes through them is used. Thus, the results obtained by the detector
from the attenuation of radiation gives information about the distribution and height of the
packing material within the column.
The present study performed in the laboratory consisted of the determination of phases
within a column packed with material of different density, to which a γ-profiling was
done by means of a source-detector system, in order to establish the interfaces of the
packing distributed within the mentioned column. A 137Cs source (10 µCi) was used,
with a scintillation detector mobilized by a stepper motor (v “ 6.6 m/s) and the packing
consisted of several types: sand and gravel, fine gravel, clay, coarse gravel, fine sand, air and
water. This experiment was carried out with two types of measurement: 2 measurements/s
and 5 measurements/s and it was demonstrated that that this technique used to estimate
packing heights and interfaces is very efficient and that with a profile made with more
measurements per second, best results with lower percentages of variation are obtained.
260 IAEA–CN–241–176
B11
Saadaoui Talk: Session B11, Thursday 10:15 B11-06
A γ-Ray Computed Tomography for Investigating the Wood
Structure
A. Saadaoui1, A. Ouardi1, F. Z. Oujebbour1, R. Alami1, and R. Outayad1
1Centre National de l’Energie des Sciences et des Techniques Nucléaires (CNESTEN), Rabat, Morocco
Corresponding Author: A. Saadaoui, saadaoui@gmail.com
The γ-ray computed tomography (CT) technique represents an effective solution for the
control of the internal of the objects and provides, after measure and appropriate treatment
of the data, a mapping of the inside of an object.
The idea is to control and to characterize the status of several trees of the forest of Mamoura.
We will begin by measuring thickness of the bark and trying to identify the rings of growth.
IAEA–CN–241–284 261
B11
ICARST–2017
B12:Radiation Techniques for Industrial Processes
Optimization and Safety II
262
B12
Thereska Talk: Session B12, Thursday 11:15 B12-01
Radiotracer Residence-Time Distribution Method in Diagnosing
Industrial Processing Units: Case Studies
J. Thereska1, E. Plasari2
1Institute of Applied Nuclear Physics, University of Tirana, Tirana, Albania
2Ecole Nationale Supérieure des Industries Chimiques, Nancy, France
Corresponding Author: J. Thereska, thereska@gmail.com
Radiotracers are unique in troubleshooting and diagnosing industrial processing units in
harsh and opaque field conditions; the success of radiotracers is primarily due to their certain
advantages such as online detection without shutting down or disturbing the process.
The paper gives examples showing how the information obtained by radiotracer experiments
is used to analyze the operation of industrial processing units, to eliminate troubles and to
optimize the performance of processes.
Radiotracer residence time distribution (RTD) measurements have been applied to inves-
tigate the pulp flow characteristics in the superphosphate production chamber using the
radiotracer 51Cr impregnated in the solid phase of the pulp in the mixing chamber; the
mathematical model constructed on the basis of the experimental RTD showed an unsatis-
factory functioning of the reactor; ways were proposed to correct this shortcoming, both in
the existing chamber and in that which was being designed for a new plant.
Characterization by radiotracer RTD of flow dynamics in laboratory and pilot-plant molec-
ular sieves columns dehydrating organic liquids is another case study. Experiments with
113mIn radiotracer in 0.01 M aqueous solutions of EDTA have been carried out to investigate
the fluid flow dynamics in columns of three different diameters filled with molecular sieve
spherical particles. The dependence of the fitting of experimental with theoretical RTDs
upon the column diameter-to-particle diameter ratio was found and rather bad fitting for
ratios smaller than 10 were observed. The influence of these phenomena on the adsorption
process was investigated.
IAEA–CN–241–029 263
B12
B12-02 Talk: Session B12, Thursday 11:30 Rawat
Investigation of the Multiple Side Injections on Hydrodynamics
of the Gas-Solids Fluidized Bed Using Radiotracer Based
Techniques
J. S. Rawat1, P. Tiwari1, H. J. Pant2, and R. K. Upadhyay1
1Indian Institute of Technology, Guwahati, India
2Bhabha Atomic Research Centre (BARC), Mumbai, India
Corresponding Author: J. S. Rawat, j.rawat@iitg.ac.in
Fluidized bed reactors are the core of the chemical industries. The contact between fluid
and solid phase plays an important role in the overall yield and performance. The liquid
injection of the reactants has tremendous application in the various industries such as
polypropylene production, catalytic cracking, coating and drying, etc. These processes
occur in the fluidized bed reactors in which precursors are added to the reactor in atomized
form through side injections. The jetting phenomena affects the system locally as well as
globally and may change the solid recirculation profile in the reactors. These recirculation
profiles contribute to the solid mixing and hence the quality of fluidization. This works
focusses on the effect of the multiple injections on the solid distribution and velocity field
via radiotracer based techniques.
The experiments are carried out at three different air inlet velocities, which correspond to
1.5, 2 and 3 Umf. For each air inlet velocity, experiments are performed with secondary
gas injection through single and two side nozzles (placed at the same and different planes)
operated at three different nozzle flow rates (80, 100, 120 LPM). Glass beads of 660 µm
size and density 2500 kg/m3 are used in all the experiments. The solid distribution and
solid velocity profiles are estimated using the γ-ray densitometry and radioactive particle
tracking (RPT) techniques, respectively. Densitometry provides line averaged attenuation
measurement for each radial location. The term “densitometry” refers to measurement
of the density of a material by determining the degree to which that material attenuates
radiation of a given energy. By using the Beer-Lambert law, the phase holdup can be
calculated along the chord length in which the attenuation in the radiation is measured. In
RPT motion of a single radioactive particle, which has same size, shape and density as of the
other particles, is tracked by using NaI(Tl) scintillation detectors. In current experiments
46Sc embedded in glass beads is used as a tracer particle.
Densitometry and RPT experiments are performed for different nozzle configurations and
flow rates. The time average radial solid distribution profile is estimated at different axial
planes. The bed is operated at 3 Umf at different nozzle injection velocities. Results indicate
that compared to without nozzle case with nozzle injection cases show higher fraction of
solids similarly, The other experimental finding will be addressed in full paper.
It was observed that most of the injected gas flow near the injection wall even at the higher
flow rate and resulting in the low solid fraction at the wall in the case of single nozzle
injection. The multiple nozzle injection (their location and configurations) have significant
impact and depending upon injection velocity the second nozzle may increase or decrease
these effects.
264 IAEA–CN–241–240
B12
Ud Din Talk: Session B12, Thursday 11:45 B12-03
Radiotracer and Sealed Source Technologies for Measurements
in Industry
G. Ud Din1
1Pakistan Institute of Nuclear Science and Technology (PINSTECH), Nilore, Pakistan
Corresponding Author: G. Ud Din, ghiyasuddin@hotmail.com
The field of radiation technology came into being right at the discovery of radioactivity in
1896 by Henri Becquerel. In the coming years, several useful applications of radiation influ-
enced the development of various radiation detector and analysis systems so that qualitative
observations can be converted to precise measurements of energy, intensity and location of
radiation. Some of these major applications include medical applications, industrial applica-
tions, high energy physics and nuclear security. Various means of development of artificial
radionuclides and their transformation to useful radiotracers were explored keeping in view
of these applications. Portable radionuclide/radiotracer generator systems were established
for on-site production of radionuclides which have proved very successful in medical and
industrial applications. The objective of this presentation is to give an overview of the ap-
plications that are driving radiation technology research for making useful measurements.
Keeping in view of the substance involved in subject research field and my special field
of research, the talk is focussed on radiation technology for measurements in industrial
applications. The principle and applications of radioisotopes for making measurements and
troubleshooting in industry will be discussed. The development of various nucleonic control
systems for on-line measurements in industry will be presented. Thin Layer Activation
technique for wear measurements in industrial systems will become under discussion. In
addition to this, radiotracer applications for industrial process optimization will also be
covered. Modern day approach for diagnosing complex industrial systems (multiphase
flow systems) using radiotracers in combination with computational fluid dynamics (CFD)
technique will also be elaborated during the presentation.
IAEA–CN–241–355 265
B12
B12-04 Talk: Session B12, Thursday 12:00 El Korchi
Radioisotope Techniques for Detection of Coking in Liquid Flow
through a Solid Phase in a Lab-Scale Distillation Column’s
K. El Korchi1, R. Alami1, A. Saadaoui1, S. Mimount1, and A. Chaouch2
1Centre National de l’Energie des Sciences et des Techniques Nucléaires (CNESTEN), Rabat, Morocco
2Laboratoire Biotechnologie Environnement et Qualité (LBEQ), Université Ibn Tofail, Kénitra, Morocco
Corresponding Author: K. El Korchi, elkorchi.87@gmail.com
The petrochemical industry is one of the most important sectors of radioisotope technology
applications. The distillation columns are considered as one of the most critical components
in oil refineries. In packed bed distillation columns, the coking phenomenon is likely to
occur inside the packing (solid) through which a liquid is flowing.
The aim of the proposed work is to try to address the coking phenomenon as a challeng-
ing issue in petrochemical industry by combining or integrating sealed radioactive source
techniques and radiotracer techniques. The results correspond respectively to tests using
two radioisotopes with γ-scanning technique and radiotracers. In the first approach, the
structural characteristics of a laboratory constructed distillation column have been investi-
gated by using the γ-scanning technique which consists in using a 60Co as a γ-ray sealed
source associated with a NaI(Tl) detector. The second approach by radiotracers consists of
an injection of an appropriate quantity of a specific radiotracer (99mTc) at the inlet of the
process and studying its presence in the column.
Results shows that the radiotracermethodmay be a good approach for detecting the presence
of coke in case of liquid flow through solid packing in distillation columns. Further, data
will be useful in numerical modelling and validation by CFD simulations.
266 IAEA–CN–241–296
B12
Goswami Talk: Session B12, Thursday 12:15 B12-05
Measurement of Residence Time Distribution of Wastewater in a
Constructed Wetland System Using Radiotracer Technique
S. Goswami1, J. S. Samantray1, D. Poswal2, S. R. Asolekar2, and H. J. Pant1
1Bhabha Atomic Research Centre (BARC), Mumbai, India
2Indian Institute of Technology, Mumbai, India
Corresponding Author: S. Goswami, 1987.goswami@gmail.com
Constructed wetlands (CW) are human engineered systems that utilize natural process for
treatment of wastewater. They have been highly applicable in developing countries, due
to their characteristics like utilization of natural processes, simple construction, operation
and maintenance, process stability, and cost effectiveness. The design of constructed wet-
land requires multidisciplinary inputs involving biological and ecological sciences, aquatic
chemistry, engineering hydrology and flow hydrodynamics. The CW are heterogeneous in
nature. Thus, they are prone to show deviation in the designed flow pattern and residence
time for the treatment of wastewater. Thus, the aim of the present study is to measure mean
residence time (MRT) and flow patterns of CWs using radiotracer technique.
The wetland is 13.0 m long, 3.0 m wide and 0.7 m deep. The geometric volume of the
system is 27.3 m3. The system walls and bottom were lined to prevent leakage. The wetland
has slope of 1% at the bottom and an average porosity of 52%. About 100 MBq of 99mTc
(τ1{2 “ 6.6 h, Epγq “ 139 keV) as sodium pertechnatate used in each run. The radiotracer
concentration monitored at different planes across the width and outlet using NaI(Tl)
scintillation detectors were connected to a computer controlled data acquisition system was
set to record tracer concentration at an interval of once per minute at outlet and across the
bed of the system.
The RTD data was treated and analyzed using a RTD analysis software. The data treatment
includes background subtraction, tail correction, radioactive decay correction, zero shifting,
smoothing and normalization. The data was used to calculate MRT, system dead volume
and hydraulic efficiency of the plant. A four-parameter model i.e., tank in series exchanging
with dead volume model prefixed with plug flow component was used to simulate the RTD
data.
Radiotracer experiments were successfully conducted in an artificially constructed wetland
system and mean residence times and dead volumes were determined at different operating
conditions. No bypassing/short-circuiting was observed in the CW. The proposed four-
parameter model was found suitable to describe hydrodynamics of wastewater in the
wetland. The hydrodynamic parameters were indicating that CW works efficiently at bed
height of 0.6 m, wastewater flow rate of 2.3 m3/s and two point distributor geometry.
However, the results of the study also indicate that on increasing the number of injection
points, the efficiency of the CW will increase.
IAEA–CN–241–062 267
B12
B12-06 Talk: Session B12, Thursday 12:30 Adzaklo
Radiotracer Investigation of the Effect of Impeller Type on
Mixing in Industrial Process Simulator
S. Y. Adzaklo1, C. P. K. Dagadu1, I. I. Mumuni1, P. S. Adu1, H. A. Affum1, G. K. Appiah1,
and A. Coleman1
1Ghana Atomic Energy Commission (GAEC), Legon-Accra, Ghana
Corresponding Author: S. Y. Adzaklo, s.yadzaklo@gaecgh.org
Radiotracer technology has been applied in the industry for the investigation of process
performance, online monitoring of conditions of process plants, troubleshooting and diag-
nosing anomalies including mixing conditions in continuous stirred tank reactors.
In this study, radiotracer methodology was used to carry out investigation on a laboratory
water flow rigwhich serves as simulator of industrial processes. The aims of the investigation
were to assess: i) the effect of impeller type onmixing, and ii) the fluid dynamics of the water
in the vessels since both the vessels and the impellers were redesigned and reconstructed.
Four similar vessels in series circuit with different impeller configurations were investigated.
Tank 1 has 1 axial impeller, tank 2 has 2 axial impellers, tank 3 has 2 radial impellers
and tank 4 has no impeller. The data was collected by introducing 8 mCi liquid 99mTc at
the inlet stream of the vessels and the γ-signal was collected with thallium activated NaI
detector placed at the outlet of the vessels. Residence time distribution (RTD) curves for the
outlet tracer concentration were generated from which the mean residence time (MRT) and
variance were calculated by the method of moments. The extent of material mixing in the
vessels was inferred from the variances and the fluid dynamics was obtained by modelling.
The extent of mixing was highest in tank 3 followed by tank 1, and tank 4 gave the poorest
mixing. The outlet response curves were fitted with mathematical models using DTS pro
and RTD Software. The best fit for tanks 2, 3 and 4was perfect mixers in series with exchange
(PMSE) model while perfect mixers in series with recycle (PMSR) model best described the
fluid dynamics of the material in tank 1.
268 Presenter: I. I. Mumuni IAEA–CN–241–372
B12
ICARST–2017
B13:Radiotracer for Managing of Natural Resources,
Energy and Processes
269
B13
B13-01 Talk: Session B13, Thursday 14:15 Jentsch
Investigation of Heavy Metal Release at a Municipal Solid Waste
Incineration Facility: An Excellent Example for the Unique
Potential of Intrinsic Radiotracer Application to the
Investigation of Industrial Processes in Chemical Engineering
T. B. O. Jentsch1
1Helmholtz-Zentrum Dresden-Rossendorf e.V., 01328 Dresden, Germany
Corresponding Author: T. B. O. Jentsch, t.jentsch@hzdr.de
Radiotracers are widespread in use for the investigation of material transport processes in
industry and environment. Often they are used for the measurement of the residence time
distribution in continuously operating chemical engineering facilities and reactors. Mostly
intrinsic or physical tracers are used for these purposes.
In case of phase transformation processes are in the focus of interest physical or extrinsic
tracers are not the labelling material of choice. Intrinsic or chemical tracers are required in
that case. At example of the heavy metal release investigation at a municipal solid waste
incineration facility the unique potential of intrinsic radiotracers will be demonstrated in
the given paper.
The goal of the investigation at the municipal solid waste incineration facility reported in
this paper was the behaviour study of different heavy metal species at various incineration
conditions. With the help of short lived radioisotopes of copper (64Cu) and zinc (69mZn)
could be shown at which position of the incinerator and in which amount the heavy metal
under investigation was released.
The experimental results of this investigation were an essential contribution for better un-
derstanding the processes inside the incinerator and to optimize the processing conditions.
270 IAEA–CN–241–302
B13
Abdullah Talk: Session B13, Thursday 14:35 B13-02
Radiotracer Investigation in an Aeration Tank of a Waste Water
Treatment Plant
J. Abdullah1, H. J. Pant2
1Malaysian Nuclear Agency, Bangi, 43000 Kajang, Selangor, Malaysia
2Bhabha Atomic Research Centre (BARC), Mumbai, India
Corresponding Author: J. Abdullah, jaafar@nm.gov.my
A radiotracer experiment was conducted in an aeration tank of a waste water treatment
plant in a chemical plant in Malaysia. 131I [τ1{2 “ 8 days, energy: 360 keV (80%), 640 keV
(9%)] as sodium iodide was selected to be used as a radiotracer. About 12.5 GBq (200 mCi)
of radiotracer was used. The radiotracer was diluted in a volume of about 30 ` and injected
into the splitter pit at a constant rate for a period of about 10 minutes using a specially
fabricated injection arrangement. This ensures good mixing of the tracer with the inlet
stream of wastewater and almost equal division of radiotracer into two individual tanks
(tank A and tank B). The period of injection is negligibly small as compared to expected
mean residence time of the wastewater in the tank and hence the tracer injection can be
considered as an impulse or instantaneous injection.
The radiotracer was monitored at different strategically selected locations using 11 water-
proof scintillation detectors (22 ˆ 22, or 50.4 mm by 50.4 mm). All the detectors were con-
nected to a common 12-channel computer-controlled data acquisition system programmed
to monitor tracer concentration data at an equal time intervals. During the acquisition,
the data was saved at regular intervals. The continuous on-line monitoring of tracer was
conducted for a period of 26 days.
Results revealed that no malfunctioning such as bypassing or short-circuiting of the flow
was observed in the tank. The mean residence time in the tank was estimated to be about
6 days, which matches with the theoretical mean residence time (hydraulic retention time).
The residence time in the membrane was negligible as compared to the residence time in the
tank. No considerable dead volume was found in the tanks. This indicated that the entire
volume of the aeration tank was used for the treatment of the wastewater. A model with a
tank connected to a dispersed plug flow component in series with a recycle flow was found
suitable to describe the flow of wastewater. The results of the model simulation showed
that the aeration tanks behave as an ideal mixer. However, the membrane behaved as a plug
flow reactor. The result of simulation indicated that the recycle flow rate is about 1.4 times
the inlet flow. The results of the investigation will help the plant engineer to evaluate the
performance of the aeration tank.
IAEA–CN–241–088 271
B13
B13-03 Talk: Session B13, Thursday 14:55 Oujebbour
Data Fusion Approach for Improving the Reliability of
Radiographic Testing and other Complementary NDT
Techniques
F. Z. Oujebbour1, S. Mimount1, R. Alami1, A. Saadaoui1, R. Outayad1, and A. Ouardi1
1Centre National de l’Energie des Sciences et des Techniques Nucléaires (CNESTEN), Rabat, Morocco
Corresponding Author: F. Z. Oujebbour, oujebbourfatimazahra@gmail.com
Non-negligible uncertainty and imprecision in defect detection and defect sizing exist when
only using one single non-destructive testing (NDT) technique. To increase the reliability
and reduce the uncertainty of defect detection and defect sizing, the complementarity and
redundancy of radiographic and ultrasonic testing data is exploited. The reliable concept to
improve the detection and characterization of defects is by combining the data sets of these
NDT techniques. This goal is achieved by employing mathematical data fusion techniques
r1, 2s. These are techniques allowing for simultaneously taking into account heterogeneous
data coming from different sources in order to get an optimal estimation and evaluation
of defects under investigation. The present study focusses on the development of a data
fusion approach based on the evidence theory (Dempster-Shafer theory) r3, 4s in order to
merge a large number of data sets, in a suitable manner, and obtain more reliable results of
localization and characterization of defects inside a component. The proposed method is
validated by a real ultrasonic and radiographic NDT data of different industrial components.
References
r1s D. L. Hall, Mathematical Techniques in Multisensor Data Fusion, MA: Artech House,
1992.
r2s X. E. Gros, NDT Data fusion, John Wiley and Sons, New York, 1997.
r3s A. Shafer, Mathematical Theory of Evidence, Princeton University Press, Princeton, NJ,
USA, 1976.
r4s A. Dempster, Upper and lower probabilities induces by multivalued mapping, Annals
of Mathematical Statistics, AMS-38, 1967.
272 Presenter: R. Alami IAEA–CN–241–244
B13
Mumuni Talk: Session B13, Thursday 15:15 B13-04
Neutron Backscatter Technique as an Alternative Method for
Quality Assurance and Standardization of Petroleum Products
I. I. Mumuni1, S. Y. Adzaklo1, H. A. Affum1, P. S. Adu1, A. S. Salifu2, K. A. Danso3, and
C. P. K. Dagadu1
1Ghana Atomic Energy Commission (GAEC), Legon-Accra, Ghana
2EWD, Tema Oil Refinery, Tema, Ghana
3School of Nuclear and Allied Sciences, Accra, Ghana
Corresponding Author: I. I. Mumuni, ishi76@yahoo.com
Crude cost is one of the most important parameters in the operation of an oil company.
The choice of crude is very vital in that it determines the profit margins of oil companies,
hence the selection of an optimum crude for processing requires careful consideration.
Neutron backscatter technique is a non-destructive method used for industrial investigation,
including determination of hydrogen content of crude and its finished product. This method
has a wide scope of application and is faster in comparison with the chemical methods
employed by the petroleum industries which are destructive, product specific and often
requires several hours of heating samples at temperatures up to 750˝C to obtain results.
Neutron backscatter technique was used in this work to determine the total hydrogen
contents of petroleum samples from Tema Oil Refinery (TOR) and crude oil samples from
the Jubilee oil field in Ghana and Bonny light and Forcados oil fields in Nigeria. Excess
neutron counts were measured and reflection parameters determined as a function of
hydrogen content of the samples. Liquid hydrocarbons of known hydrogen and carbon
contents were used as standards to draw calibration curves against which the total hydrogen
contents of the samples were determined.
The total hydrogen contents were found to be in the range of 7.21–15.06 (hw%) for vertical
geometry and 7.20–14.94 (hw%) for horizontal geometry respectively. The results agreed
well with other results obtained using different methodologies. The results shows a high
hydrogen content in both Nigeria’s Bonny light and Ghana’s Jubilee crude oil samples
however, in Nigeria’s Forcados crude oil sample there was a low hydrogen content. This
confirms that neutron backscatter technique is able to distinguish between light sweet crude
and heavy sour crude.
IAEA–CN–241–074 273
B13
B13-05 Talk: Session B13, Thursday 15:35 Hlaing
Identification of the Internal Condition of Crude Oil Distillation
Unit Using γ-Column Scanning Technique in Myanmar
M. P. Hlaing1, K. Y. Lwin1
1Department of Atomic Energy (DAE), Nay Pyi Taw, Myanmar
Corresponding Author: M. P. Hlaing, moephyu.hlaing@gmail.com
The γ-column scanning technique was utilized to identify of mechanical problems such as
missing, collapsed or buckled trays in trayed column of Crude Oil Distillation Unit C at the
No. (1) Refinery (Thanlyin), Yangon, Myanmar. It has 52 trays, diameter is 2 m and height
is 43.55 m. Scanning type of work is Blank Scan and this unit has been shutdown since
2010 due to some processing problem. The refinery wanted to know internal condition
of a column before operation. The scanning work was performed using a 50 mCi 60Co
γ-source, NaI(Tl) scintillation detector, manipulation system (winchers) and ColScanCK1
Data Acquisition (DAQ) system with NibraS software to investigate condition of all trays.
By reference to the mechanical drawing of the tower, the point at elevation of 7350 mm was
assigned as starting point of the scan and it was denoted as 0 mm. Three scan lines were
selected; one for single pass trays and two for double pass trays within the left and right
down comer areas of the Distillation Unit. The Radiation source was placed at 44˝, 59˝ and
107˝ and detector was placed at 224˝, 291˝ and 224˝, respectively.
It was challenging to scan because the space between insulator and ladder is very narrow,
in some places detector and source were passed the ladder with considering of radiation
safety aspect. Although size of tray #1 to 8 are very small and wall of column is very thick
in these place, we could determine tray #1 to #8 were in their positions. From identification,
all scan profiles interpreted that tray #1 to #52 were normal and in their positions.
274 IAEA–CN–241–034
B13
ICARST–2017
B14:Radiation for Cultural Heritage Characterization
275
B14
B14-01 Talk: Session B14, Thursday 16:30 Boutaine
A Survey of the Possibilities of Various Radiographic
Techniques for the Non Destructive Examination of Cultural
Heritage Artefacts
J. L. Boutaine1
1Centre de Recherche et de Restauration des Musées de France (C2RMF), Paris, France
Corresponding Author: J. L. Boutaine, jean-louis.boutaine@wanadoo.fr
How, where and when artefacts were manufactured, how they were exchanged, when,
where and how techniques appeared, prospered or disappeared, what has been their
evolution and/or degradation during time, are topics of increasing interest. How can we
better understand art objects and cultural heritage artefacts and keep them available, in
best condition, for future generations is a very significant challenge. Due to the broad
diversity of materials, and as the artefacts have various, often complex and undetermined
compositions, as their elaboration processes are often unknown or at least uncertain, it is
generally necessary to combine various examination, characterization and analysis methods,
to get pertinent information and thus to give a rational basis for their restoration and
conservation. Furthermore, because of the unique or rare nature of cultural heritage artefacts,
as a general rule, the techniqueswhich can be usedmust be eitherwell tested and proven non-
destructive and noncontact methods without any sampling, or tests with strictly authorized
small size sampling Radiography has long been applied to medical diagnosis and to non-
destructive examination of industrial objects. In the area of cultural heritage, it has proven
to be invaluable for the examination and the study of works of art.
In a first part, a brief survey will be given of the basic physics principles of the different
possible variants of the radiographic techniques. They include: conventional X-ray radiogra-
phy, γ-radiography, radiography using accelerator, radioscopy, β-radiography or secondary
electron radiography, electron emission radiography, neutron radiography, autoradiography
and computer assisted tomography. Many major types of artefact collections are concerned
by radiographic examination: easel paintings (X-ray, electron emission, autoradiography),
ceramics (X-ray), stone, metal and wooden statues (X-ray and γ-ray, tomography), paper and
drawings (α particles and secondary electrons), archaeological objects (various techniques),
musical instruments (X-ray and tomography).
The second part will provide examples of applications of these different techniques on
various types of artefacts, focussing on issues related to the study of historical fabrication
techniques, the diagnosis of eventual previous restoration and of the object’s condition.
If this palette of techniques, eventually associated with complementary NDT techniques,
is used by a competent and skilled technician, and if there is a real dialogue between
himself and the curator, or the conservator-restorer, or the art historian, or the historian of
techniques, or the archaeologist, it can provide many pertinent elements, contributing to a
deeper knowledge of the artefact and insure a conservation process as pertinent as possible.
276 IAEA–CN–241–427
B14
Gichuru Talk: Session B14, Thursday 16:45 B14-02
Application of Ionizing radiation in Studying Akaba and Masai
Art Objects Made from Glass
M. J. G. Gichuru1, D. M. Maina1, M. J. Mangala1, S. W. Karuga1, F. K. Kariithi1, and
S. Bartilol1
1Institute of Nuclear Science & Technology, University of Nairobi, Nairobi, Kenya
Corresponding Author: M. J. G. Gichuru, mgatari@uonbi.ac.ke
Glass is known to deteriorate under environmental conditions and therefore it is of major
concern to conservationist, cultural heritage fans and museum institutions. However, glass
art products are common wares, made and sold by artists in the low-income groups of
different Kenyan communities. They are therefore an economic asset and income provider
formany poor households. For the authorities tomake a decision on how to help the involved
artists and resellers, to add value to their products and capture a wider market, especially
from tourist and business visitors, a better understanding of product structure, morphology
and elemental content was seen to be necessary. Ionizing radiation instrumentation are
good tools for this kind of study and therefore XRF and radiography facilities at the Institute
of Nuclear Science and Technology were used to analyze randomly purchased objects from
street hawkers and market resellers. The spectra and radiographs will be analyzed and the
resultant data used to assess the source of deterioration and give informed recommendations
to policy makers and stakeholders in the business.
IAEA–CN–241–376 277
B14
B14-03 Talk: Session B14, Thursday 17:00 Ekinci
Radiographic Investigation of Archaeological Objects
Ş. Ekinci1
1Turkish Atomic Energy Authority, Çekmece Nuclear Research Center, Istanbul, Turkey
Corresponding Author: Ş. Ekinci, sinasi.ekinci@taek.gov.tr
Radiography is a versatile technique with many applications to archaeological and art
historical artefacts. It can be used to assess the condition of objects before conservation or
restoration treatment, to gain information of materials used and methods of construction,
and to reveal the secrets of the embalmer’s art, hidden within mummified remains. The
techniques can be applied to materials as diverse as papers, fabric, wood, ceramic and
metal, as well as to human and other animal remains. Radiographic examination basing
on film imaging or digital imaging techniques may provide images of objects concealed
within a mass of corrosion and may even reveal a previously unknown painting, hidden
beneath a later work. All of this can be carried out non-destructively, making radiography
an invaluable tool for the study of cultural materials.
Radiographic investigations of the archaeological objects at Çekmece Nuclear Research and
Training Centre were carried out since 2004 in collaboration with Archaeology Museum of
Istanbul and Directorate of Istanbul Central Laboratory for Restoration and Conservation.
This work describes radiographic investigations of the archaeological objects in order to
support museums, laboratories and archaeology specialists for the restoration, conservation
and replica processes, as well as inventory purposes. Film based, flat panel and imaging
plate radiographic techniques were used in the examinations. Some of the investigated
objects in this study are anchors of 13th Century of Byzantine Empire taken out from a
wracked excavation, chains used in the Golden Horn during the period of Byzantine Empire,
head of the Snaky Statue from Roman Period being situated in Sultan Ahmed Square in
Istanbul, metal objects from Bathonea excavation in Istanbul, etc.
Findings obtained from the examined objects were assessed together with archaeology
specialists in order to make comment about their history and production methods and to
decide for the restoration and conservation processes.
The use of radiographic examination for the preservation of cultural heritage became a
very important tool that allows scientists and archaeologists to accurately identify and
conserve items that would have been lost or damaged in the past. The results obtained from
this study were very beneficial for the Istanbul Archaeology Museum and Conservation
and restoration Laboratory for determining the internal structure and surface condition of
the objects before treatment for restoration, conservation, replica works and a lot of other
processes.
278 IAEA–CN–241–365
B14
Artemiev Talk: Session B14, Thursday 17:15 B14-04
Using X-Rays to Detect Hidden Images (Old Masters) on Priming
Canvases
B. Artemiev1, I. Artemyev1
1ZAO “RII-MSIA” “Spectrum”, 119048, Moscow, Russian Federation
Corresponding Author: B. Artemiev, boris@artemiev.su
Improving the radiation technology: enhancing the stability of the sources, the possibility
of fine adjustment of the anode voltage, emission control range and high sensitivity and
stability of detectors allow the use of this equipment for the detection of latent images on
canvases (paintings).
Experience in the use and methods of application of this equipment to solve the problem
of detection of illegal movement of works of art. The presentation will discuss emerging
issues and their solutions.
IAEA–CN–241–136 279
B14
B14-05 Talk: Session B14, Thursday 17:30 Outayad
Some Applications of X-Rays in the Service of the
Archaeological Site of Volubilis
R. Outayad1, S. Mimount1, and R. Alami1
1Centre National de l’Energie des Sciences et des Techniques Nucléaires (CNESTEN), Rabat, Morocco
Corresponding Author: R. Outayad, outayadrabie@gmail.com
The studies done during this work are part of the collaboration agreement between the
Ministry of Culture and CNESTEN. Investigative studies, diagnosis and characterization
of a cultural archaeological heritage, carried out before any repairs or restoration and
conservation. The studies are to implement two approaches combined namely industrial
radiography X and PMI (positive material identification) for quantitative and qualitative
evaluation of a variety of archaeological items on the site of Volubilis. These two comple-
mentary methods allowed us firstly to evaluate the condition of structures for possible
restorations, mobilizations and characterize in situ controlled materials without sampling.
280 Presenter: R. Alami IAEA–CN–241–250
B14
De Beer Talk: Session B14, Thursday 17:45 B14-06
Secrets and Mysteries of our Past Revealed by Neutron and
X-Ray Radiography/Tomography
F. De Beer1
1South African Nuclear Energy Corporation (Necsa), P.O. Box 582, Pretoria, South Africa
Corresponding Author: F. De Beer, frikkie.debeer@necsa.co.za
Heritage is our legacy from the past, what we live with today and what we pass on to future
generations. Our cultural and natural heritages are both irreplaceable sources of life and
inspiration. Places as unique and diverse as also the wilds of East Africa’s Serengeti, Cradle
of Humankind in South Africa, the Pyramids of Egypt, the Great Barrier Reef in Australia
and the Baroque cathedrals of Latin America make up our world’s heritage. What makes
the concept of World Heritage exceptional is its universal application. World Heritage sites
belong to all the peoples of the world, irrespective of the territory on which they are located.
It is a universal need to reveal those important and in most cases hidden features of findings
such as artefacts or fossils in a noninvasive manner in order to preserve, sometimes only
artefact ever found, in the most a responsible manner for future generations to also study
with possible new developed analytic techniques.
Currently, neutron and X-ray based analytical techniques play an important role in both
applied research and practical applications. Today, various experimental setups of neutron
techniques can be used effectively for imaging purposes. Moreover, recent developments
of X-ray methods, which are used primarily for medical applications, like diagnostics or
treatment (e.g., X-ray based computer tomography, tomotherapy, image guided radiother-
apy, etc.), use advanced imaging principles. However, both neutron and X-ray imaging
techniques do not offer directly analysis of elemental composition of studied entities. One
important application of neutron and X-ray radiation based imaging techniques is the non-
invasive study on objects from cultural heritage importance, where these probes reveal
valuable hidden information in a non-destructive and noninvasive manner.
The aim of this presentation is to highlight the non-destructive analysis of cultural artefacts
using the capabilities of neutrons and X-ray’s as penetrating probes. Several case studies
will be discussed about neutron and X-ray radiography and tomography investigations of
cultural artefacts being practiced at various research institutions worldwide.
IAEA–CN–241–445 281
B14
B14-07 Talk: Session B14, Thursday 18:00 Bensitel
The Radiography in the Service of the Preservation of the
Moroccan Historical Heritage
A. Bensitel1, R. Alami1, and K. Bourchouk2
1Centre National de l’Energie des Sciences et des Techniques Nucléaires (CNESTEN), Rabat, Morocco
2Musée Archéologique de Rabat, Division des Musées,
Direction du Patrimoine Culturel Marocain, Ministère de la Culture, Rabat, Morocco
Corresponding Author: A. Bensitel, ab.bensitel@gmail.com
Moroccan historical heritage is extremely rich and varied. The historymore thanmillennium
of Morocco bequeathed us objects of the heritage going of the prehistoric and antique Art to
the Amazighe and Arab-Islamic art by way of Greco-Roman period. Numerous objects of
the Moroccan heritage suffer from a doubtful state of preservation, even critical in certain
cases.
It is consequently indispensable to develop and to apply techniques of examination, charac-
terization and analysis of the oeuvres of art of the Moroccan cultural heritage, constituent
materials of these works, to know the mechanisms of their elaboration, their evolution
and/or degradation and establish recommendations with the aim of their restoration and
of their preservation. For that purpose, we privilege the non-destructive methods, without
contact (when possible), without sampling. Among these methods, some make use of
X-rays and the γ-rays. These methods, the only ones or associated with other techniques
are applied to very diverse works and materials of all kinds, any origin and any age.
The application of X-ray radiography in numerous pieces of the Archaeological Museum of
Rabat, in particular the statue of Ptolémée (marble), a Roman ceremonial helmet (bronze), a
pyxidium with relief (bone) so allowed:
• To estimate the area and the extent of the damages undergone by these objects;
• To contribute to a better knowledge of the techniques of manufacturing by the artists
having realized these works as well as the previous restorations made on the studied
pieces;
• The assistance-advice for the benefit of the curators and the restorers for the estab-
lishment of specific methodologies of restoration to every type of object.
The radiography also allows the contribution to the establishment of detailed identification
sheets of valuable museum pieces, particularly those being often the object of loans between
museums.
282 Presenter: R. Alami IAEA–CN–241–391
B14
ICARST–2017
B15:Advances and Trends in Radiotracer and
Radiation Science and Technology II
283
B15
B15-01 Talk: Session B15, Friday 09:00 Bjørnstad
Nuclear-Based Monitoring of Industrial Mass Flow I: The
Potential Use of Small Transportable Neutron Generators
T. Bjørnstad1
1Institute for Energy Technology, Norway
Corresponding Author: T. Bjørnstad, tor.bjornstad@ife.no
Radiotracers for industrial monitoring are produced mainly by two main methods: 1) Ac-
tivation in research nuclear reactors (RNR) or at charged particle accelerators, and 2) by
radiotracer generators (RG). Both methods face challenges:
1. The production by activation is often difficult from both administrative and technical
reasons. Administrative reasons imply that the production of specific radionuclide
has to be known and authorized at the irradiation facilities. Technical reasons imply
that irradiation facilities are often non-existing in many countries. Where irradiation
facilities do exist, there are limitations due to periodical shut downs. Finally, trans-
portation time between irradiation facilities and industrial site limits again the use of
short half-life radiotracers.
2. The number of commercially available radiotracer generators for industrial use is
rather limited for the moment. Other options for nuclear-based monitoring of indus-
trial mass flow that appear may therefore be interesting to pursue.
One such option is the application of recently developed small-sized neutron generators.
Two types of neutron generators are available using deuterium-deuterium (DD) reaction
(neutrons at 2.45 MeV) and deuterium-tritium (DT) reaction (neutrons at 14.1 MeV). Com-
mercial DT generators may produce neutron outputs of ą1011 n/s. Unlike isotopic neutron
sources, the neutron generators contain no radioactivity (except the inventory of tritium
in the DT neutron generator) making them inherently safe (no external radiation) when
turned off.
This presentation will review the current status of such neutron generators and discussed
possible applications for use in industrial in situ or even on-line monitoring processes.
The various approaches include on-site production of radiotracer by off-line irradiation
of suitable target, on-line and in situ generation pulses of short-lived radiotracers from
macroelements in the flow, direct continuous activation of matrix elements in the flow, acti-
vation of injected pulse of a stable chemical compound, PGNAA of injected non-radioactive
tracer pulse, neutron transmission measurement after pulse injection of a strong neutron
absorber and others. The broad industrial use of such techniques is at present in its infancy,
and a considerable R&D work remains to be done to ensure the robustness of the different
approaches.
284 IAEA–CN–241–430
B15
Bjørnstad Talk: Session B15, Friday 09:10 B15-02
Nuclear-Based Monitoring of Industrial Mass Flow II: The
Potential Use of Small Transportable Neutron Generators
T. Bjørnstad1
1Institute for Energy Technology, Norway
Corresponding Author: T. Bjørnstad, tor.bjornstad@ife.no
Radiotracers have been widely used throughout industry to optimize processes, solve
problems, improve product quality, save energy and reduce pollution. Stricter regulatory
regimes lately demand, however, that the radioactive labels are as short-lived as practically
possible in order to reduce radiation load to personnel involved. This requirement introduces
some challenges. Short half-lives limit the permissible transportation time from radionuclide
production facilities like nuclear reactors or particle accelerators. Thus, the use of tracer
technology in process monitoring on remote industrial sites is hampered. One remedy to
cope with this problem is to develop and apply radiotracer generators based on radionuclide
generators. These are again based on suitable and specific mother-daughter nuclear genetic
relationships with a long-lived mother and a short-lived daughter.
This presentation describes various types of generator principles from column-based equip-
ment where the mother nuclide is fixed on a solid support and the daughter is eluted in an
external liquid, systemswhere themother radionuclide is exclusively dissolved in one of two
immiscible liquids and where daughter separation takes place in a liquid-liquid extraction
process, to systems where the mother is a gas and the daughter a solid (or the other way
around) and where the separation process includes a cryogenic step. The presentation also
describes which generators are commercially available today for industrial monitoring, and
which type of development work is needed to extend the selection of desirable generators.
IAEA–CN–241–431 285
B15
B15-03 Talk: Session B15, Friday 09:20 Datta
Residence Time Distribution Measurements in Industrial Scale
Reactors with Recycle Using Radiotracer Technique
A. Datta1, S. Goswami2, R. K. Gupta1, H. J. Pant2, V. K. Sharma2, H. Bhunia1, and
D. Singh3
1Thapar University, Patiala, India
2Bhabha Atomic Research Centre (BARC), Mumbai, India
3IOL CP, Trident Complex, Barnala, India
Corresponding Author: A. Datta, arghya.datta@thapar.edu
All process industries go through a series of routine steps to produce economically viable
products. The rawmaterials are initially made to go through a number of physical treatment
blocks to be converted into the form which is conducive for the chemical reactions. They
are then introduced to the reactors where chemical reactions occur and the products are
formed. Lastly, the products are separated, purified, etc., and the desired commercial grade
products are obtained. Reactors, in this whole process, play the most important part in
any process industry and better reactor efficiency results in better product quality. The
ideal reactors are: batch reactor, continuous stirred tank reactor and plug flow reactor.
Recirculation reactors are a type of continuous stirred tank reactors where the mixing of the
reactants is done by the turbulence created by the recirculation stream. These are employed
where the installation of agitators in the reaction vessel is not desirable like bio-reactors,
nuclear reactors, etc. The mixing process of such reactors can be optimized by residence
time distribution studies. It helps in determining the non-ideality of the reactors for instance,
dead zones, channelling or short-circuiting and the extent to which it deviates from ideality.
Once known, the information can be used to increase the reactor efficiency by tweaking
the reactor geometry and an accurate model can be derived to describe the working of the
reactor. In process industries, usually single pass conversions are low and the reactants are
recycled back to the rector to achieve high overall conversion. Developing models from
residence time distribution data obtained from recycle reactor are relatively complex and
literature references are also scarce as the input to the system (recycle) changes to a random
input.
Residence time distribution studies are performed by injecting a suitable radiotracer in the
ethyl acetate reactor as a pulse, measuring the output signal and plotting the residence time
distribution of the reactor. Bromine, 82Br as ammonium bromide, with a half-life of 36 h
and good compatibility with the contents inside the reactor yet unreactive, was chosen as
radiotracer. It was introduced online as a pulse input into the feed line of a recirculation
reactor producing ethyl acetate via a reversible equilibrium-limited esterification reaction.
The reactor had recycle streams coming from two different distillation columns containing
unreacted reactants.
After the output concentration of radiotracer was plotted against the time, preliminary
observation of the residence time distribution curves showed the presence of internal recir-
culation, which was obvious as the reactor worked on the principle of internal recirculation
for proper mixing of contents.
286 Presenter: R. K. Gupta IAEA–CN–241–194
B15
Arahmane Talk: Session B15, Friday 09:40 B15-04
Neutron-γ Discrimination Using Non-Negative Matrix
Factorization Blind Sources Separation Algorithms
H. Arahmane1, E. M. Hamzaoui2, and R. Cherkaoui El Moursli1
1Mohammed V University, Rabat, Morocco
2Centre National de l’Energie des Sciences et des Techniques Nucléaires (CNESTEN), Rabat, Morocco
Corresponding Author: H. Arahmane, hanane_ar1@hotmail.com
In this study, we apply blind sources separationmethods (BSS) based on non-negativematrix
factorization techniques (NMF) to extract independent components from signals recorded
at the output of fission chamber detectors. Since these modern signal processing methods
require no hypothesis on the way that the signal and the noise are mixed, encouraged us
to apply these methods to reach n–γ discrimination in a soft way. For that reason, we use
Geant4 as nuclear simulator, to model the neutron detection system installed inside the
TRIGA MARK II Reactor (Nuclear Facility of the Moroccan National Center for Nuclear
Energy, Sciences and Techniques). The fission chamber is used in a research nuclear and
a flux-mapping experiment is performed. We use the simulated fission chamber’s output
signals as time series mixtures that will be analyzed through non-negative and blind sources
separation algorithms. The computation of performance index of each blind separation
method will allow us to select the most efficient NMF algorithm that permit to achieve the
best n–γ discrimination. In addition, the computation of the auto and cross-correlation
functions, the power spectral densities and time-frequency decomposition of the resulting
independent components will provide a better characterization of these nuclear signals
with very high precision.
IAEA–CN–241–367 287
B15
B15-05 Talk: Session B15, Friday 10:00 Yang
Contrabands Detection with a Low Energy Electron Linac Driven
Photoneutron Source
Y. Yang1
1Tsinghua University, Haidian, Beijing, People’s Republic of China
Corresponding Author: Y. Yang, yangyigang@mail.tsinghua.edu.cn
A low energy electron linac driven photoneutron source, which can provide both X-rays and
photoneutrons simultaneously in the same system, is realized to interrogate contrabands
concealed in luggage or cargoes. X-rays produced by the 7 MeV electrons that bombard
the tungsten target are used to penetrate the inspected material and form the 2D mass
thickness image. Photoneutrons, which are the by product of X-rays, can be used to penetrate
the inspected materials to form the neutron image. The fusion of the X-ray image and
photoneutron image is helpful for the separation of organic materials, light metals, medium-
weight metals and heavy metals. The (γ,fission) induced β-delayed neutrons in the heavy
metal indicates the possible existence of the special nuclear material. Photoneutrons within
the eV energy range can then be used to penetrate the heavy metal in order to identify its
isotopic concentration, if it is suspected as the special nuclear material. The thermalized
neutron can also induce the prompt γ-rays in the inspected material, the detection of which
provides the fingerprint information of special nuclides, which in turn helps the detection
of explosives or drugs. This system can be held in a truck, and hence is a mobile system
that can provide in situ contrabands detection abilities.
288 IAEA–CN–241–446
B15
Francus Talk: Session B15, Friday 10:20 B15-06
Combining CT Scan and Particle Imaging Techniques:
Developing New Applications to Sediment Transport
P. Francus1
1Institut national de la recherche Scientifique (INRS), Québec City, QC G1K 9A9, Canada
Corresponding Author: P. Francus, pierre.francus@ete.inrs.ca
Physical models were built to study sediment transport in coastal and fluvial environ-
ments. X-ray computed tomography (CT) technology has useful applications in geosciences
providing density and porosity of non-homogeneous materials. The medical CT scanner
is interesting because of its large opening, allowing a field of view up to 65 cm for the
reconstructed image. Dynamic systems could also be studied with the CT scan by do-
ing temporally resolved measurements. This project uses optical imaging techniques to
characterize the effect of different flow types (i.e., uniform flow and waves) on sediment
transport.
A movable sand-bed model was built in the Multidisciplinary Laboratory of CT Scan for
Non-Medical Use at the INRS (Québec, Canada). A rectangular flume (0.30ˆ 0.30ˆ 7.0 m3)
made with 25 mm thick transparent acrylic material was inserted into a medical X-ray CT
scanner (Siemens, Somatom Definition AS+ 128). The CT scanner moves on 2.6 m rails
along the flume. For preliminary tests, the water depth in the flume is 0.14 m. The sand bed
is composed of quartz (SiO2), Ottawa sand, with grain median diameter (d50) of 217 µm
and uniform density. The bed height is 5 cm. In addition, as the examination table is static
and the gantry moves along the object, the use of large fixed physical models is possible.
Steady flow can be created using a water pump joining the two water tanks placed at each
extremity of the flume. A honeycomb diffuser reduces the turbulence at the water inlet.
A wavemaker can also be installed at one extremity to generate waves. A wave absorber
made of angular pebbles is placed at the other extremity. A particle image velocimetry
(PIV) measurement system is mounted on the CT scanner allowing time-synchronized and
co-located measurements. The camera is protected from the X-ray by a lead sheet.
The method consists of coupling a medical CT scanner and a particle image velocimetry
(PIV) system. The two datasets are combined to provide an image with density values as
well as velocity vectors, and the the PIV system can be successfully synchronized with the
CT scanner. With this settings, fundamental information can be gained to understand the
physics of particle-fluid dynamics and improve the modelling of the underlying processes.
This experimental apparatus allows for the parametrization of shear velocity and sediment
density at the boundary layer, which is an essential but otherwise difficult to determine
parameter of sediment transport.
IAEA–CN–241–434 289
B15
ICARST–2017
B16:Technical Cooperation Success Stories: Country
Reports
290
B16
Rodolfo Talk: Session B16, Friday 11:15 B16-01
The Participation of the Technological National Centre in the
Technical Cooperation Programme Activities
K. M. Rodolfo1
1Centro Tecnológico Nacional (CTN), Talatona, Luanda, Angola
Corresponding Author: K. M. Rodolfo, rkabeymbaz@yahoo.com
TheNational Technological Centre (CTN)with headquarter in Luanda, is a public institution
tutored by the Ministry of Science and Technology, focussing on applied scientific research.
This paper aims to inform the success of the participation of CTN in the cooperative activities
between Angola and the IAEA through the Technical Cooperation Programme. The purpose
of the cooperation is to help the country to build, strengthen and maintain human and
institutional capacities for the safe, peaceful and secure use of nuclear technology in support
of national development, and activity that the CTN has pursued since 2006.
To achieve the proposed goals, three main phases have been set up in the projects implemen-
tation: outward specialists visits (from other latitudes), human resources empowerment and
training (member mobility in the projects) and laboratory equipment acquisition (creation
of laboratory-based infrastructure). With this program, the CTN was able to set up labo-
ratories for non-destructive testing and radioisotope tracing. Around 20 project members
were trained in renowned centres in different regions. Through these laboratories, the
CTN has accrued the capacity of radioisotope tracers application in oil industrial as well as
the use of non-destructive techniques to improve quality of industrial goods and service.
In terms of contributions to socio-economic development in the country, in the process
of empowerment and training of science, technologies and innovation system’s actors in
Angola, the CTN through this laboratories trained 21 trainees in non-destructive test, level I,
in penetrant testing, magnetic particle testing, ultrasonic testing and radiography testing,
9 are working now in local companies, and another group of 5 trainees are training on
radiotracer techniques in CTN.
Future prospects are to empower human recourses in various techniques to use the maxi-
mum potential of machines existing in the Centre to solve practical problems and address
basic human needs. The cooperation concept always ends up in a win-win. From experience,
the CTN thinks that feedback is not significant enough in term of sponsorship assessment
but this does mean it will never be noticeable. It cannot appear at this initial time, it will
surely.
IAEA–CN–241–263 291
B16
B16-02 Talk: Session B16, Friday 11:35 Abdullahi
Progress, Problems and Prospects of Radioisotope Technology in
Nigeria
A. S. Abdullahi1
1Centre for Energy Research and Training (CERT), Ahmadu Bello University, Zaria, Nigeria
Corresponding Author: A. S. Abdullahi, saarabi@abu.edu.ng
Nigeria as a member state of the IAEA has benefited immensely in the field of radioiso-
tope technology through the agency’s support in manpower development, deployment
of relevant equipment and other relevant support towards the Centre’s desire to setup an
Industrial Isotope Technology (IIT) laboratory at the CERT, Ahmadu Bello University (ABU),
Zaria. The Center has organized many training courses in this regard, among these is the
National Seminar organized in collaboration with the Kaduna Refinery and Petrochemical
Company Limited (KRPC) hosted by CERT and supported by the IAEA. This national
conference was held on 12th to 16th August, 2013 which saw a large number of participant
mainly from the oil and gas industries in attendance. Nigeria with its position as one of the
top nine oil exporters worldwide, with five functional refineries, eleven licences issued for
construction of new refineries, a host of other process related industries and thousands of
kilometers of pipelines transporting crude and refined petroleum products that crosscut the
country, is believe to be an ideal terrain for radioisotope technology application. This paper
highlights the progress, evaluates the problems and prospects of this technology in Nigeria.
292 IAEA–CN–241–027
B16
Baricholo Talk: Session B16, Friday 11:55 B16-03
Industrial Application of Radioisotopes in Zimbabwean
Industries: A Report on RTD Experiments in Cement Industry,
Radon Monitoring in Coal and Fly Ash of a Small Thermal
Power Plant and NDT Activities
P. Baricholo1, P. Sithole2
1National University of Science and Technology, Bulawayo, Zimbabwe
2Radiation Protection Authority of Zimbabwe (RPAZ), Harare, Zimbabwe
Corresponding Author: P. Baricholo, pbaricholo@gmail.com
Major activities carried out Zimbabwe with support from the IAEA towards industrial
applications of radioisotopes are presented. Radiotracer 198Au was used to determine the
residence time distribution (RTD) of limestone and clay in the production of clinker at PPC
Colleen Bawn factory near Gwanda with the objective of determining hold-up and grinding
efficiencies of a ball mill operating in a closed circuit regime. Three experiments were
conducted using 198Au and highly sensitive NaI(Tl) detectors for radiation measurement.
In two experiments, 50 mCi of 198Au was used to tag limestone and clay which were fed into
the ball mill at 85 tonnes/h and 90 tonnes/h, respectively. In the other experiment 100 mCi
of the tracer was used to tag limestone with a feedrate of 90 tonnes/h. The estimated
efficiency of the separator of nearly 90% showed that the performance of the separator is
satisfactory. It was concluded that the grinding process of raw materials inside the mill was
not optimal.
In order to determine the amount of γ-radiation released to the environment by coal-fired
thermal power generation and environmental γ-radiation levels we have monitored radon
concentrations in a coal powered thermal power station (ZPC Bulawayo). Results obtained
suggest that there were no high radon concentrations in the coal nor in the fly ash produced
by the power plant. Four IAEA Fellows in NDT are currently doing their fieldwork before
certification. NDT field work activities using radiography, ultrasound and liquid penetrate
techniques were carried out and details of the field work carried out are presented.
IAEA–CN–241–353 293
B16
B16-04 Talk: Session B16, Friday 12:15 Mallillin
Computed Tomography for Characterizing Industrial Materials
J. Mallillin1, D. Aquino1
1Philippine Nuclear Research Institute (PNRI), Quezon City, 1107 Metro Manila, Philippines
Corresponding Author: J. Mallillin, jpmallillin@pnri.dost.gov.ph
Computed tomography (CT) is a noninvasive technique that can provide two-dimensional
cross-section image and information on the internal structure of an object including ab-
normalities and their dimensions using spatial measurements across it. CT has been long
used and is well established in the medical and NDT applications but because of emerging
technologies and through research and development, it is now carried out for industrial ap-
plications. CT is a powerful tool of quality control and has shown a wide range of industrial
applications in mechanical, plastic and chemical and ceramics industry. The benefits that
the technology offers to industries make γ-ray CT an interest for research and development
endeavours.
This paper reports the capability of a first generation γ-ray CT system is characterizing
different material in terms of the density distribution along the cross section of each sample.
Measurements were taken from samples of wood, industrial steel piper and polyethylene
products using a single-source, single-detector system and images were recreated using
an image reconstruction software. Reconstructed images show relatively good representa-
tions of the actual samples that provide a qualitative density distribution along the object
cross section. With further refinement and optimization of measurement parameters and
review of reconstruction algorithms, the technique could be a useful tool for inspection and
troubleshooting in a variety of industries.
294 Presenter: D. Aquino IAEA–CN–241–426
B16
Omondi Talk: Session B16, Friday 12:35 B16-05
Measurements of Radiotracer Residence Time Distribution
Using a Flow Rig in Kenya
C. Omondi1, D. Otwoma2
1Kenya Bureau of Standards (KEBS), Nairobi, Kenya
2National Comission for Science, Technology and Innovation (NACOSTI), Nairobi, Kenya
Corresponding Author: C. Omondi, cyallar@kebs.org
The Kenya Bureau of Standards (KEBS) in partnership with IAEA has set up a radiotracer
data analysis measurements facility using a flow rig under Project RAF/0/004:“Cleaner and
Safer Management of Industrial”. The purpose of the facility is to promote the radiotracer
residence time distribution (RTD) method extensively to industries, in order to optimize
processes, solve industrial problems, improve product quality, save energy and reduce
pollution. The radiotracer methodology includes the accurate measurement of the RTD and
its utilization for troubleshooting and diagnosis. The process involve injecting a compatible
radiotracer into an appropriate inlet upstream of the flow rig vessel and monitoring its
passage through, therefore allowing fluid RTD to bemeasured. Sensitive radiation detectors,
are placed at strategic elevations and locations on the flow rig. The scintillation detectors are
used because they are relatively small and easy to mount at each position. Each scintillation
detector is connected by a cable to a central data logging device that records radiotracer
concentration versus time information. The data acquisition system ensures collection, treat-
ment and visualization of the data. When the radiotracer passes each detector a response is
registered and recorded. Before the investigation, each detector is assessed and its response
normalized so that each detector responds identically to a given unit of radiotracer. The
flow rig consists of a tank with four stirrers, a pump flowing the water inside the rig, two
flow meters for measuring flow rates in two different branches, several two and three way
valves for regulating the flow direction and regime, two injection points, pipes and ion
exchange resin column for trapping the radiotracer after a test. The radiotracer used is
99mTc with relatively low activity for each test. From the results, different flow patterns
are then simulated using the flow rig. The investigations performed are dead volume mea-
surement, by-pass measurement, determination RTD measurements that include parallel
flow measurements, re-circulation experiment, pump mixing and flow rate. The important
features and benefits of radiotracers above conventional methods is that measurements can
be made while a plant is on-line, with no disruption to operating processes.
IAEA–CN–241–386 295
B16
ICARST–2017
PA1: Posters PA1: Irradiation Facilities and their
Applications
296
PA1
Abaza Session PA1, Wednesday 14:15 PA1-01
New Trends in Radiation Dosimeters
A. Abaza1
1Egyptian Nuclear and Radiological Regulatory Authority (ENRRA), Cairo, Egypt
Corresponding Author: A. Abaza, aya_abaza@hotmail.com
A radiation dosimeter is a device that measures exposure to ionizing radiation. It has two
main uses: for human radiation protection and for dose measurement in both medical
and industrial processes. The personal ionizing-radiation dosimeter is of fundamental
importance in the disciplines of radiation dosimetry and radiation health physics and
is primarily used to estimate the radiation dose deposited in an individual wearing the
device. Workers exposed to radiation, such as radiographers, nuclear power plant workers,
doctors using radiotherapy, those in laboratories using radionuclides, and HAZMAT teams
(personnel specially trained to handle dangerous goods, which include materials that are
radioactive, flammable, explosive, corrosive, oxidizing, asphyxiating, biohazardous, toxic,
pathogenic, or allergenic) are required to wear dosimeters so a record of occupational
exposure can be made. Such devices are known as “legal dosimeters” if they have been
approved for use in recording personnel dose for regulatory purposes. Dosimeters can be
worn to obtain a whole body dose and there are also specialist types that can be worn on
the fingers or clipped to headgear, to measure the localized body irradiation for specific
activities. The aim of this study is to identify and highlight the new technology in the types
of radiation dosimeters.
The study comprises a personal selection of recent reports from radiology journals and the
results of Medline searches which highlight new trendS in radiation dosimeters. Radiation
dosimeters and dosimetry systems come in many shapes and forms, and rely on numerous
physical effects for storage and readout of the dosimetric signal. The four most commonly
used radiation dosimeters are: ionization chambers; radiographic films; thermolumines-
cent dosimeter systems (TLDs); silicon diode dosimetry systems (Diodes). However, there
are a variety of electronic personal dosimeters, extremity dosimeters, and comprehensive
dosimetry management systems to monitor the exposure to ionizing radiation at any work
environment. It can get an effective dose monitoring when and where we need it. Electronic
dosimeters protect the wearer from the harmful effects of radiation by tracking changes in
exposure and keeping an ongoing record of the user’s dose over time. Combinedwith access
control systems, it is possible to limit total exposure to radiation and control access to radio-
logical areas. Dosimetry readers ensure accurate radiation exposure monitoring. Manual
and automated systems for whole body, extremity, neutron, and environmental monitoring
are easy to operate, service, and maintain. Extremity dosimeter is a disc dosimeter designed
for nuclear power or nuclearmedicine personnel that have a high risk of exposure to ionizing
radiation, particularly on their hands, due to their work in close proximity to radiation
materials and radiation producing equipment.
IAEA–CN–241–327 297
PA1
PA1-02 Session PA1, Wednesday 14:15 Abdelgawad
Setting up of New Radiation Facilities in Alexandria, Egypt
S. Abdelgawad1
1National Center for Radiation Research and Technology (NCRRT), Nasr City, Cairo, Egypt
Corresponding Author: S. Abdelgawad, sherifag_2004@outlook.com
The γ-Irradiation Facility (400 kCi) from Isotope Hungry is the only unit in Alexandria
capable of sterilizing medical and agricultural products as well as industrial irradiation
research and applications. The activity of this 60Co facility could be increased to (2 MCi)
in order to meet the market demand for irradiated food and healthcare products. Such an
upgrade seems to be sufficient for the wide demand of medical companies especially those
who are going to increase their export capacity of irradiated medical products.
298 IAEA–CN–241–414
PA1
Abdullah Session PA1, Wednesday 14:15 PA1-03
In Situ and Non-Destructive Detection of Oleoresin in Standing
Agarwood Trees Using Portable γ-Ray Tomography Imaging
System
J. Abdullah1, H. J. Pant1, M. R. Shari1, H. Hassan1, H. Ithnin1, and A. A. Mahmood1
1Malaysian Nuclear Agency, Bangi, 43000 Kajang, Selangor, Malaysia
Corresponding Author: J. Abdullah, jaafar@nm.gov.my
Agarwood is known for its fragrant resinous wood. It is a rare and precious oleoresin on
the planet, prized for its rich and wonderful fragrance and healing properties. Because
of its high economic value, agarwood has been subject to intensive exploitation in South
East Asia’s natural forest for hundreds of years. Consequently, agarwood-producing tree
species have become extremely rare. The extinction threat to agarwoods is becoming more
worrisome because their harvest is often done by trial and error; specifically, by cutting
standing trees without any reliable means to detect and confirm the presence of oleoresin.
This practice is not only inefficient and technically and economically ineffective, but it also
contradicts sustainable forest management principles.
To decrease random harvesting, technological innovation is needed to detect the presence
of oleoresin within the trees. Technology based on the measurement of γ-ray attenuation to
assess internal trunk or wood characteristics has been developed. The attenuation of γ-rays
is highly correlated to the atomic number and density of materials. The principle of this
technology is based on measuring and recording the transmitted intensity of γ-rays that
pass through the tree trunk. The transmitted γ-ray intensities will differ depending on the
density of the wood. Since the presence of oleoresin in agarwood changes the density of
trunk wood, this technology can theoretically detect agarwood within a tree.
A portable clamp-on γ-ray tomography system, called GammaSpider, was designed and
manufactured by scientists and technologists at the Centre for Computed Tomography and
Industrial Imaging in the Malaysian Nuclear Agency. This paper presents the results of
tomographic imaging of several standing agarwood trees of different ages. In addition, the
effectiveness of inoculation process to produce oleoresin was also evaluated. Computed
tomography (CT) images of the samples were obtained at 1.25 mm resolution. Besides
a clear distinction between oleoresin, void and wood fibre, some bright white areas oc-
curred in the reconstruction images caused by a denser medium component in the wood,
apparently oleoresin deposits that attenuated the radiation. This technique demonstrates a
potential application of γ-ray computed tomography in the detection of oleoresin in stand-
ing agarwood trees. The development of GammaSpider was carried out in an attempt to
provide an alternative non-destructive means to the conventional cutting methods for the
detection of oleoresin in standing agarwood trees. The system has produced quality images
with excellent contrast, which shows clear and correct representation oleoresin, void and
wood fibre. From the CT images, the positions and extent of oleoresin could be precisely
quantified. The scanner has been successfully used for non-invasive detection of oleoresin
in agarwood trees in a number of field tests in plantations in Malaysia. The successful
utilization of this innovative has been recognized both nationally and internationally, as
GammaSpider has won a number of awards. The method offers great advantages for in situ
inspection of agarwood tress as compared to the conventional methods. Work is continuing
on improvements to meet the demands of faster scanning.
IAEA–CN–241–086 299
PA1
PA1-04 Session PA1, Wednesday 14:15 Adjerad
Facilitating Sustainable Education in Nuclear Science and
Technology
A. Adjerad1
1Centre de Recherche Nucléaire d’Alger (CRNA), Alger-Gare, Algeria
Corresponding Author: A. Adjerad, athmanead@yahoo.fr
Many e-learning tools are currently available for using in education, however, the environ-
ment for nuclear education is changing. Teaching methods and techniques have evolved
as have enrollment trends in science and engineering studies. E-learning is regarded as
the most modern and cost effective means to supplement traditional face-to-face education,
and the way forward to provide more opportunities to access valuable information and
knowledge regardless of time and place.
In this paper, we review the new learning methodology, potential challenges of e-learning,
the author e-learning tools and the different e-learning tools such as educational platforms
and web-based meetings. We also comment on the most important aims of each tool and
define the advantages and the disadvantages.
An educational platform is effective in e-learning development but does not provide social
networks. However, the web-based meeting is an innovative collaboration solution provid-
ing an exceptional experience with the simplicity of a web browser, easily and naturally.
The overall objective is to contribute to improving the sustainability and quality of nuclear
education process and recommended best practices to improve efficiency and effectiveness
300 IAEA–CN–241–193
PA1
Aljohani Session PA1, Wednesday 14:15 PA1-05
Pilot-Scale Study of the Radiation-Induced Silica Removal from
Underground Brackish Water in Saudi Arabia
M. Aljohani1, F. Djouider1
1King Abdulaziz University, Jeddah, Saudi Arabia
Corresponding Author: M. Aljohani, mjohani@kau.edu.sa
Brackish underground water desalination is the second main water supply, after seawater
desalination, used in the Kingdom of Saudi Arabia. Most of the inland cities and villages rely
entirely on this supply mode for their domestic industrial and agricultural purposes. High
silica concentrations are found in these waters and can cause an excessive and recalcitrant
deposit on the membrane, fouling the reverse osmosis (RO) units. This membrane fouling is
a worldwide problematic issue in the cost-effective operations in water desalination plants.
In this work, we investigated the effectiveness of γ-radiation induced removal of silica in
water sample from the Salbukh water treatment plant (near Riyadh, Saudi Arabia). A 60Co
source was used to γ-irradiate the acidic pH solution containing silica mixed with metal iron
powder and saturated with pure oxygen gas before irradiation. The radiolytically produced
hydroxyl radicals OH‚ oxidize the iron metal into ferric ions which co-precipitate with the
silica resulting in the removal of the latter.
The influence of several reaction parameters, i.e, iron powder dosage, radiation dose, initial
pH and equilibriumpH effects were investigated. The removal increasedwith the irradiation
dose and reached a plateau at 350–400Gy. For a percentage removal as high as 75% obtained
in this work, the optimal conditions of the main reaction parameters studied here, were as
follows:
• optimum initial pH is 2–3;
• the removal increased with increasing pH up to the pKa of the silicic acid.
• Fe0 dosage: 8 g/l.
This preliminary study showed that this environmentally friendly γ-radiation process is
effective in silica removal from underground water. This process could be implemented in
arid regions in Saudi Arabia, where population has a limited access to fresh water.
IAEA–CN–241–219 Presenter: F. Djouider 301
PA1
PA1-06 Session PA1, Wednesday 14:15 Baccaro
Radiation Activities at ENEA Calliope γ-Facility
S. Baccaro1, A. Cemmi1
1Agenzia nazionale per le nuove tecnologie, l’energia e lo sviluppo economico sostenibile (ENEA), Rome, Italy
Corresponding Author: S. Baccaro, stefania.baccaro@enea.it
Since the eighties, the Calliope γ-irradiation facility (Casaccia R.C., Rome, Italy) was deeply
involved inmany research activities, in the framework of international projects and collabora-
tions with industries and research institutions, focussed on the investigation of γ-irradiation
effects on chemical and physical properties of different materials. The Calliope Facility, lo-
cated in the ENEA-Casaccia Research Centre, is a pool-type irradiator equipped with a 60Co
cylindrical γ source array (mean energy of 1.25 MeV) in a high volume (7.0ˆ 6.0ˆ 3.9 m3)
shielded cell. The plant is equipped with dosimetric services and a monitoring system for
logging the irradiation time, allowing accurate calculation of the absorbed dose in materials.
Available dosimetric systems include Fricke, Red-Perspex, alanine-ESR and TLD. Different
irradiation dose rates, from zero to a maximum of some kGy around the rack longitudinal
axis, are available by placing the sample in specific position within the irradiation cell. The
irradiation tests can be performed in air or inert atmosphere, or under vacuum.
Several research and qualification activities, in compliance with international standard spec-
ifications, were carried out at the Calliope facility. Irradiation and dosimetric certifications
are issued by the Calliope facility after each irradiation test. Qualification tests are mainly
performed on electronic components and devices for application in hostile environments
(nuclear plants and aerospace) and on concrete matrices for nuclear waste disposal and
storage. The Calliope facility is indicated by the Italian Space Agency ASI as ASI Supported
Irradiation Facility (ASIF), recommended by the European Space Agency ESA.
Synthetic and natural polymeric materials used in many fields (e.g., nuclear and space
application, medical devices, food packaging, cultural heritage) are studied in term of γ-
induced processes (cross-linking and degradation). The behaviour is evaluated in different
atmospheric conditions (air, vacuum or inert gases), paying particular attention on the
irreversible modification occurring during or after the end of γ irradiation.
At the Calliope laboratory, research for cultural heritage material conservation and preser-
vation (books, images) centre on biological deteriogen eradication by γ radiation and the
assessment of recovery procedures. Other biological studies relate to agriculture and the
environmental, such as biological pest control via γ irradiation (sterile insect technique: SIT)
and agricultural product treatment.
Activities concerning polymers and biological applications on cultural heritage are carried
out in the framework of IAEA Coordinated Research Project F23032 (Research Agreement
No.18922/RO, 2015–2019). The Calliope laboratory has several instruments for the evalua-
tion of scintillating material performance by optical (UV-VIS and FTIR spectrophotometer,
luminescence measurements), spectroscopic (ESR spectrometer) and light yield measure-
ments in term of number of photoelectrons emitted per unit of absorbed energy. Great
expertise has been achieved on radiation detectors, optical components and scintillators
(optical fibres, crystals and glasses) applied in High Energy Physics experiments, such as
CMS ECAL experiment at LHC CERN and Belle II experiment at SuperKEKB (Japan).
302 Presenter: A. Cemmi IAEA–CN–241–032
PA1
Bai Session PA1, Wednesday 14:15 PA1-07
Detoxification of High Toxicity Substances by Radiation
Transformation Technique
H. Bai1, J. Kim1, and B. Y. Chung1
1Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
Corresponding Author: H. Bai, hbai@kaeri.re.kr
Developing a new pharmaceutical substance takes a large amount of time, money and effort
over the full process. Usually, translation of a promising molecule into an approved drug
takes more than 10 years. Therefore, there is pressure advance techniques to reduce the
time and cost. We have attempted to develop radiation fusion technology for transforming
toxic substances such as abandoned drugs and naturally occurring polyphenols, known
to be toxic, in order to reduce their toxicities. About 200 substances were exposed to γ-
irradiation, resulting in 18 compounds generatedwith low toxicity compared to their mother
compounds. For instance, rotenone, isolated from roots of derris plant, was reported as
an anticancer agent. However, recent studies have demonstrated that rotenone has the
potential to induce several adverse effects such as a neurodegenerative disease. Radiolytic
transformation of the rotenone with γ-irradiation created new products, named rotenoisin A
and rotenoisin B, monitored by HPLC and purified by column chromatography. It was
found that rotenoisin A and B were potent anticancer candidates (similar to the parent
rotenone) for breast and hepatic cancer cells, respectively, without toxic effect to normal
cells even at high concentrations when compared to rotenone. These results suggest that
the radiolytic transformation of high toxicity compounds by γ-irradiation may be a good
strategy for modifying the structure and decreasing the toxicity of the parent compound.
More systematic structural modifications together with γ-irradiation will be performed
in the future to further clarify these interesting findings in order to develop even more
promising anticancer candidates.
IAEA–CN–241–182 Presenter: J. Kim 303
PA1
PA1-08 Session PA1, Wednesday 14:15 Bergaoui
Evaluation of Radiation Shield Integrity of DD Neutron
Generator Facilities by Monte Carlo and Experimental Methods
K. Bergaoui1, N. Reguigui1
1National Center for Nuclear Sciences and Technologies (CNSTN), Sidi Thabet, Tunisia
Corresponding Author: K. Bergaoui, bergaoui.kaouther@gmail.com
A new deuterium-deuterium (DD) neutron generator has been installed for a wide range of
applications. The generator is an excellent fast, epithermal and thermal neutron source for
laboratories and industrial applications that require neutrons but with safe operation, small
footprint, low cost and small regulatory burden. The generator has three major components:
a radio frequency induction ion source, a secondary electron shroud, and a diode accelerator
structure and target. Monoenergetic neutrons (2.5 MeV) are produced with a maximum
yield of 1010 n/s using 25–50 mA of deuterium ion beam current and 125 kV acceleration
voltage.
Detailed knowledge of the radiation dose rates around the neutron generator are essential
for ensuring radiological protection of the personnel involved with the operation. This work
describes the Monte Carlo and experimental studies carried out in the Neutron Generator
facility of the National Center of Nuclear Sciences and Technologies (CNSTN). Verification
and validation of the shielding adequacy was carried out by measuring the neutron and
γ-dose-rates at various locations inside and outside the neutron generator hall during the
operational conditions and comparing the results with theoretical simulations. A successful
operation of this generator will provide a convenient neutron source for basic and applied
research at CNSTN.
304 IAEA–CN–241–041
PA1
Betesho Babrud Session PA1, Wednesday 14:15 PA1-09
Fungal Decontamination of Historical Oil Painting by Using
γ-Ray
R. Betesho Babrud1, N. Sheikh1, and F. Khatamifar1
1Atomic Energy Organization of Iran (AEOI), Tehran, Islamic Republic of Iran
Corresponding Author: R. Betesho Babrud, rbetesho@aeoi.org.ir
Preserving historic heritage is the duty of a nation that cares about its history. Canvas based
paintings are mainly subject to fungal infestation under improper conservation conditions.
The aim of this study was the evaluation of optimal γ-ray dose for fungal decontamination
of a XIXth century historical oil painting (3.03ˆ 1.60 m2) stored in the Melal museum of
Sa’dabad Palace. Sampling was done from 31 points of the discoloured points via wet sterile
swab, then surface cultured on SDA medium. Fungi growth was determined after 8–12
days incubation at 29˝C. Classification was based on overall morphological properties. The
colours used were identified with infrared spectroscopy (mid and far regions). Canvas type
was identified by flame testing the fibre: type of burning, burning behaviour when away
from the flame, burning smell and ash type.
Fungi resistance to irradiation was investigated on strips made of similar canvas painted
with the same colours. Light-thermal ageing of strips were done in a QUV/Spray device
powered with fluorescent lamp with the emission maximum of 0.71 W/m2 for UVB 313 nm,
at 60˝C for 100 h, 4 h in 100% relative humidity at 50˝C. Aged strips were inoculated with
spore suspensions and exposed to 0.2–2 kGy of γ-rays from 60Co in GC220, dose rate of
2.08 Gy/s calibrated with Fricke dosimeters. Surviving spores were cultured and counted
after 5 days. D10was determined by graphing survival populations after a series of radiation
doses. Irradiated strips with 5–25 kGy were subjected to sterility test. The minimum dose
in which fungal growth is detected after 14 days of incubation in maximum two tests out of
20 was the sterilization dose.
Sampling indicated that Penicillium andAspergilluswere common fungi of the front and the
back and between canvas and the frame. Infrared spectroscopy revealed that burnt umber
brown and vagone green earth were common colours used in the painting. Checking the
fibre showed that linen was the board type. The mean D10 value of Penicillium crysogenum
ATCC12690 and Aspergillus niger CBS 104.57 on aged coloured linen strips was 0.9–1 kGy.
There were differences between D10 values on culture medium (0.41 and 0.34 kGy for
Penicillium andAspergillus respectively) and canvas stips (0.9–1 and 0.9 kGy for Penicillium
and Aspergillus, respectively) and no significant differences on aged and unaged strips.
Aged strips showed better capacity for spore recovery (1.7%) compared to unaged (0.15%).
This may be due to nutrition production during the ageing process. Sterility test indicated
that a minimal dose of 5 kGy was sufficient for sterilization of strips with 2.7ˆ 106 colony
forming units (cfu) of each fungus. The colour measurement of aged and irradiated samples
will be studied later. In conclusion and according to fungal contamination of the painting,
the dose of 5 kGy is suitable for decontamination.
IAEA–CN–241–111 305
PA1
PA1-10 Session PA1, Wednesday 14:15 Betesho Babrud
The Study of γ-Ray Efficiency in Converting Tehran Municipal
Sewage Sludge into a Sanitary Fertilizer
R. Betesho Babrud1, K. Ghotbikohan1
1Atomic Energy Organization of Iran (AEOI), Tehran, Islamic Republic of Iran
Corresponding Author: R. Betesho Babrud, rbetesho@aeoi.org.ir
The reuse of urban sewage water and sludge in agriculture leads to the transfer of some
pollutants into the food chain which is hazardous to public health. Sewage sludge samples
are from Shahid-Mahallati wastewater treatment plant in North-East of Tehran-Iran. The
heavy metals (As, Mo and Zn analyzed by graphite furnace atomic absorption spectrometry
(GF-AAS), Hg by a hybrid system, and flame atomic absorption used for Pb, Cd, Cu, Cr and
Ni), pathogens (fecal coliforms, Salmonella, Ascaris ova) and shelf life of irradiated sludge
samples according to heterotrophic mesophilic bacteria and their resistance to radiation
were investigated in this paper before and after 10, 25 and 50 kGy γ-irradiation from 60Co
over a period of three months. However, sewage sludge is a rich source of organic matter
and nutrients but agricultural utilization of this material is limited by excessive quantities
of heavy metals. In this paper the results obtained showed these elements were below the
maximum permitted levels of EPA standard and comply with Environmental Pollution
Agency standards.
The pathogen counts reduced to the permitted level after exposure to 10 kGy. This dose had
the efficiency of reducing 6 log numbers of heterotrophic mesophilic bacteria (as irradiation
indicator) but exposure to 50 kGy inhibited the regrowth of the bacteria for 80 days of study.
Bacterial resistance (D10) was between 0.02–3.09 kGy. About 0.074% of studied bacteria
had D10 of 2 kGy or more. The obtained result showed that 10 kGy of γ-rays destroyed
Salmonella. The number of fecal coliforms (dominant bacteria in human faeces) in this study
were in acceptable limit before irradiation and γ-rays cause a significant reduction in their
numbers (ttest, ρ “ 0.05). Among the helminths of sludge, Ascaris has the most resistant
eggs to physical and chemical treatment, in this research the number of fertile Ascaris eggs
in the sewage sludge (385{4 g), were more than EPA requirements before irradiation but
10 kGy γ-rays caused a reduction to an acceptable limit (ă 1 egg/4 g) so that there were no
fertile eggs in irradiated studied samples. The odor of samples reduced by increasing dose
to the point that 50 kGy irradiated samples had no odor.
According to the measurements, irradiation by 10 kGy converted the studied sludge from
class B (studied municipal sewage sludge) to class A biosolids which means that it can be
applied to agricultural lands, public contact sites and home gardens. If the sludge is not
used immediately after the treatment, the storage time should be regarded. Vector attraction
reduction processes must be conducted before use. The capability of the mentioned γ-
ray dose in converting municipal sewage sludge into a sanitary fertilizer depends on the
microbial contamination level, especially on the numbers of viable Ascaris eggs.
306 IAEA–CN–241–093
PA1
Carvalho Filho Session PA1, Wednesday 14:15 PA1-11
The Application of Radiochemical and Isotopic Studies to
Inform on the Impact of Acidic Effluent Discharges from the
Caldas UraniumMine into Neighboring Surface Waters
C. A. D. Carvalho Filho1, R. M. Moreira1
1Brazilian Nuclear Energy Commission (CNEN), Rio de Janeiro, Brazil
Corresponding Author: C. A. D. Carvalho Filho, cacf@cdtn.br
Located in the Poços de Caldas Plateau, in the southeast of Brazil, the Caldas Uranium
Mine is being decommissioned. The uranium ore consists of uranium oxides, sulfide and
zirconium minerals, fluorite, rare earth phases and molybdenum-bearing minerals. The
main environmental problem in the site is the generation of acid mine drainage (AMD) due
to the presence of sulfide minerals in the ore and in the host rocks. Acidic effluents flow
from a tailings dam, from the open pit and from waste rock piles. The study evaluates the
influence of these effluents on the surrounding surface water courses. Twelve sampling
stations were established in order to carry out the investigation. Two of them were located
inside two effluent retention ponds: the tailings pond that collects the effluents percolating
from the major waste rock pile at the site, and the settling pond immediately downstream
from the tailings dam. The remaining stations were located downstream and upstream
of the mine. Sampling was performed in the rainy and dry seasons in 2010 and 2011.
Electrical conductivity and pH were measured in situ; uranium and sulfate concentrations
were determined by ICP-MS and by liquid chromatography, respectively. Radiochemical
procedures were used to measure the 226Ra, 228Ra and 210Pb activity concentrations. The
lighter 18O and 2H isotopes were determined by isotope ratio mass spectrometry. 238U
was estimated to be 12.3 Bq/mg of uranium mass. Samples from the ponds exhibited high
median values of SO2´4 (1301 mg/`), electric conductivity (1788 µS/cm), 238U (« 109 Bq{`),
226Ra (0.49 Bq/`), 228Ra (0.47 Bq/`), 210Pb (0.70 Bq/`), and low pH (3.6). The effluents
from the tailings dam pond presented a more enriched isotopic composition (δ18O“ ´2.6‰
and δ2H“ ´18‰) than the other sampling stations, while the opposite was noticed in the
pond collecting the waste pile effluent (δ18O“ ´7.1‰ and δ2H“ ´44‰). The results also
indicated that acidic effluents from the ponds were entering the surrounding downstream
watercourses, causing a significant increase in the acidity, electric conductivity, sulfate
concentration, and 238U, 226Ra and 228Ra activity concentrations. The variation of δ18O
and δ2H values along the watercourses suggests that: waste pile effluent discharges caused
a depletion of 2H and 18O in the waters downstream; tailings dam effluents have enriched
the stable isotope composition of the waters downstream. These results can be relevant to
the stakeholders and to the authorities responsible for the site remediation. The authors will
continue to carry out studies on the site, emphasizing the identification of acidic effluent
underground leakage points. In future work, tracers, radiotracers and isotopes will be
used, contributing to the dissemination of these techniques as important tools for solving
environmental problems, with focus on those arising from the mining industry.
IAEA–CN–241–121 307
PA1
PA1-12 Session PA1, Wednesday 14:15Chmielewska-Śmietanko
Application of Electron Beam for Preservation Biodeteriorated
Cultural Heritage Paper-Based Objects
D. Chmielewska-Śmietanko1, U. Gryczka1, W. Migdał1, and K. Kopeć2
1Institute of Nuclear Chemistry and Technology (INCT), Warsaw, Poland
2Faculty of Chemical and Process Engineering, Warsaw University of Technology, Warsaw, Poland
Corresponding Author: D. Chmielewska-Śmietanko, d.chmielewska@ichtj.waw.pl
Paper provides the ideal nutrient base for mold fungi, thus, biodeterioration is the most
common source of degradation of paper-based materials in museums and libraries. Appli-
cation of electron beam irradiation in the field of cultural heritage preservation is a very
promising alternative to the commonly used ethylene oxide treatment, which is toxic to
humans and the environment. Moreover, electron beam irradiation can be effectively ap-
plied for decontamination of biodeteriorated archives as well as for preventive conservation
of large volumes of books in short time. However, to gain public acceptance for radiation
methods in large-scale applications, many analytical techniques must be used in order to
determine possible changes of mechanical, chemical and physical properties of treated
objects. Complex study of material properties before and after radiation decontamination
should ensure degradation monitoring and process validation.
In this work, the influence of electron beam irradiation for microbiological decontamination
of paper-based objects was evaluated. Connections between electron beam irradiation doses
and a change of some chemical, optical and thermal properties of different kinds of paper
were established. Electron beam radiation inactivation patterns of different microorganisms
present in different paper materials were studied as well. The samples were exposed to
electron beam irradiation using a 10 MeV–10 kW linear electron accelerator “Elektronika”
and dosimetric analysis necessary for the proper realization of the process was performed
with application of Riso B3 thin-film dosimeters as well as graphite calorimeters.
A wide range of doses, from 0.4 kGy up to 25 kGy, were studied in order to determine
safe and simultaneously effective dose for different papers decontamination via electron
beam. Changes in all sample properties were determined according to the relevant ISO and
TAPPI standards. Microbiological investigation confirmed that a dose of 5 kGy completely
eliminate all studied kinds of bacteria (gram-positive and gram-negative) as well as fungi in
Whatman CHR 1 paper, newsprint paper and office paper. Optical parameters for all studied
papers are stable for materials irradiated with doses not higher than 5 kGy, however, colour
coordinates are still changing with time after irradiation and the effect is being evaluated.
Investigation of optical parameters of the paper after irradiation confirmed that coordinate
b˚ is the optical parameter the most sensitive to electron beam irradiation, what means that
paper samples irradiated with high doses became more yellowish. The control samples
and the irradiated samples show similar thermal stability in air on heating. Taking into
account even high levels of microbiological contamination (in the order of 105 cfu/cm2) of
paper-based objects electron beam irradiation with doses of 5 kGy ensures elimination of
harmful microorganisms and simultaneously prevents paper materials degradation.
This work was supported by the IAEA Research Contract No. 18493 and by the Polish
Ministry of Science and Higher Education, project “Electron Beam for Preservation of
Biodeteriorated Cultural Heritage Paper-Based Objects”.
308 IAEA–CN–241–073
PA1
Coretchi Session PA1, Wednesday 14:15 PA1-13
Using of Radiation Sterilization
L. Coretchi1, I. Bahnarel1
1National Centre of Public Health, Academy of Sciences of Moldova, Republic of Moldova
Corresponding Author: L. Coretchi, coretchiliuba@gmail.com
There are two general types of radiation used for sterilization, ionizing radiation and non-
ionizing radiation. Ionizing radiation is the use of short wavelength, high-intensity radiation
to destroymicroorganisms. This radiation can come in the form of γ or X-rays that react with
DNA resulting in a damaged cell. Non-ionizing radiation uses longer wavelength and lower
energy. As a result, non-ionizing radiation loses the ability to penetrate substances, and can
only be used for surfaces sterilizing. For enforcement of the Law on State Supervision of
Public Health and the Law on the safe deployment of nuclear and radiological activities
in Moldova, we developed the scientific technology on ionizing radiation of products of
different origin on the base of International Standard ISO 11137 with adaptation at the
country needs and specific. This scientific elaboration specifies requirements for validation,
process control and routinemonitoring in the radiation sterilization andwill be implemented
under the IAEA coordination.
It is stipulated that the following sources of ionizing radiation can be used: γ radiation from
radionuclides 60Co or 137Cs; X-rays generated by machines operated from a nominal energy
(maximum photons energy) less than or equal to 5 MeV; electrons produced by machines
operated from a nominal energy (maximum energy of electrons) less than or equal to 10MeV.
High energy rays damage the DNA of living organisms and make them unable to grow or
reproduce. The elaboration stipulated that the mean total dose of absorbed radiation (kGy)
(maximum) for the treatment of dried herbs, spices and vegetable products consist up to
10 kGy. EB and γ sterilization are planned to be used for medical devices. From experience
of other countries is known that both methods are equally effective, but EB is more powerful
and hence the exposure time of the device is lower.
During irradiation, certain parameters of the irradiating unit (according to legal metrology
standards) must be controlled and continuously recorded. For installations using radionu-
clides, the parameters include product transmission speed or time spent in the radiation
zone and indications confirming correct position of source. For accelerator facilities, the
parameters include product transport speed and energy level, electron current and the
width of barrier installation. Before starting the irradiation for a certain category of food
minimum/maximum dose level can be determined by performing dose measurements
throughout the product volume. These validation measurements must be carried out in
sufficient numbers (e.g., 3–5 times) to account for variations in density or geometry. The
dose reference position will be quantitatively correlated with minimum/maximum dose.
The reference position is to be situated in a convenient place, where dose variations are
reduced. If fluid unpackaged products are irradiated, minimum and maximum dose can-
not be determined. In this case, it is preferable to conduct surveys to determine the dose
extremes.
IAEA–CN–241–358 309
PA1
PA1-14 Session PA1, Wednesday 14:15 Costa
Relevant Safety Aspects for Radioactive Tracers in Industrial
Process
M. L. Costa1, R. Gomes1, J. D. R. Lopes Gomes1, Z. Thomé2, and E. L. Costa1
1Brazilian Nuclear Energy Commission (CNEN), Rio de Janeiro, Brazil
2Instituto Militar de Engenharia, Rio de Janeiro, Brazil
Corresponding Author: M. L. Costa, mara@cnen.gov.br
The use of radiotracers plays an important role to provide methods to optimize industrial
process and improve product quality. An increase in the use of radiotracer investigations
has been observed in Brazil, however, as there is no specific standard for the licencing of
these facilities, generic radiation protection regulations have been used, but these are not
comprehensive nor technically suitable for this purpose. Regulatory inspections carried out
in radiotracer facilities have reported failures to follow best practices for radiological safety,
mainly in radioactive waste management and in the control of workplaces during radio-
tracer injections. In this work, an assessment of radiation protection aspects of radioactive
tracers, not covered by generic regulations, is presented, with the aim of contributing to
the future development of specific safety regulations in Brazil. The study is based on an
assessment of the licencing process of facilities using radioactive tracers in Brazil, as well as
the experience of regulatory inspections carried out at facilities using radiotracers and a
review of international standards, in order to point out relevant radiation safety aspects in
the establishment of regulatory standards for working practices, procedures and protective
measures before, during and after injections of radioactive tracers.
Among the relevant key aspects and actions for radiological protection in radiotracer in-
vestigations, we can point out: 1) Detailed radiological protection procedures, including
storage,should be elaborated for operations before, during and after injection, taking into
account: i) The different radiotracer injection strategies; ii) The available monitoring and
decontamination equipment; iii) The complete injection apparatus should be checked for
proper functioning including pressure tests before tracer injection. iv) A water injection
through the injection apparatus and connected equipment should be performed for an
extended period to clean out any contamination traces before disconnecting injection appa-
ratus. 2) The facility should have a Radiation Safety Officer (RSO) certified by the Regulatory
Authority, specifically for radiotracer applications. The RSO should not be subordinate to
operational groups. 3) Personal alarm monitors should be mandatory for each radiotracer
worker; for non-uniform exposures, it may be necessary to wear additional, e.g., hand,
dosimeters. 4) Survey tests should be performed in order to ensure successful decontami-
nation in all areas that have been contaminated by radioactive material. Equipments that
cannot be decontaminated at the jobsite should be properly packaged and sent to the field
station for further cleaning or storage. Additionally, calculations should also be made on the
impacts of any possible discharge into the environment, identifying the exposure pathways
in order to ensure agreement with authorized limits of national regulations.
The lack of a specific regulatory standard for radioactive tracer operation licencing in Brazil
weakens the nuclear regulatory body in its aim of regulating and licencing the activity.
In this study recommendations are presented concerning relevant aspects of radiation
protection for radiotracer applications, discussing specific features that should be part of the
future regulations, with the purpose of ensuring safety during radiotracer investigations.
310 IAEA–CN–241–317
PA1
Djouider Session PA1, Wednesday 14:15 PA1-15
Radiation Induced Environmental Remediation of Toxic Cr(VI)
Heavy Metal in Aerated Neutral Solution under Simulated
Industrial Effluent
F. Djouider1, M. Aljohani1
1King Abdulaziz University, Jeddah, Saudi Arabia
Corresponding Author: F. Djouider, fathid@yahoo.com
Chromium(VI) heavy metal is a major water contaminant in most industrial effluents, due
to its carcinogenicity and its impact on ecosystems, while Chromium(III) is non-toxic and
is an important element for human metabolism. Cr(VI) can be reduced to Cr(III) by the
superoxide O´2 ‚ free radical radiolytically produced in aerated solution at neutral pH in the
presence of formate.
The degradation of Cr(VI) was investigated by steady-state γ-irradiation using a 60Co source
and by pulse radiolysis using a van de Graaff accelerator in aerated solution at neutral pH,
which is close to natural conditions in most wastewaters.
The degradation of Cr(VI) increased linearly with the absorbed dose and was significantly
enhanced by the added formate but not by the radiolytically produced hydrogen peroxide
at this pH. The rate constant for this reduction was found to be 1.28ˆ 108 M´1s´1 and the
absorption spectrum of Cr(V) transient species was obtained. A partial recovery of Cr(VI)
is observed over a period of „ 5 ms following a second order kinetics with a rate constant
8.0ˆ 106 M´1s´1.
These outcomes suggest that γ-irradiation of Cr(VI)-contaminated wastewaters and indus-
trial effluents in presence of formate can be simple, effective and economical means for the
remediation of this major contaminant.
IAEA–CN–241–217 311
PA1
PA1-16 Session PA1, Wednesday 14:15 Docters
Intergrating Management Systems to Good Irradiation Practices
within a Framework of Social Responsibility
A. Docters1, M. Lucuix1, and C. Caldez1
1Comisión Nacional de Energía Atómica, (CNEA), Buenos Aires, Argentina
Corresponding Author: A. Docters, adocters@gmail.com
For more than 50 years, commercial radiation processing has been used for healthcare
products, food and other applications with a main goal in common, which is adding
value to products, achievable only if predetermined specifications are met. Technology,
process control, standards, quality management systems and personnel training, are some
of the many branches which constitute good irradiation practices which should lead to
safe and quality products. The introduction of Management Systems for Facilities and
Activities (IAEA’s GS-R-3), which through the integration of safety, health, environmental,
security, quality and economic elements in a single structure, establishes requirements to be
met in order to ensure the protection of people and the environment, enables irradiation
facilities to work with unified objectives. The further incorporation of social responsibility
principles into the overall management activities helps to increase credibility to society, and
motivate and promote commitment of workers, an essential factor to develop safety and a
good irradiation practice culture, by understanding actions generate impact on products,
environment, organization, employees, community and other stakeholders.
The implementation of social responsibility at CNEA’s irradiation facility (PISI) was orig-
inally set out with three main objectives: its integration to safety, health, environment,
quality and good irradiation practices management systems; relationship consolidation
with community and stakeholders; and as an instrument to deploy potentials in different
areas by increasing its human capital. This process was divided into three phases. The
research phase consisted in selection of the ISO 26000 standard; the identification of overall
applicable regulatory framework, including international treaties and further evaluation of
our degree of compliance; and formulation of an implementation plan. The training and
awareness activities consisted of a thorough study of principles and core subjects defined
in the standard. The planning of the application phase was based on the need to prioritize
the increase of human capital as it is the main actor in PISI’s activities, which included
training the senior management team to strengthen governance as well as activities to im-
prove communications, relationships, teamwork, staff motivation and exercise of individual
and group self-evaluation, and promoting participation in continuous improvement of
processes. Other activities included worker’s biopsychosocial health care, the identification
of stakeholders and expectations, and so on.
Relevant results were the elaboration of a shared vision statement and values between
members of PISI; strengthening of governance performance; increase of commitment; devel-
opment of self-evaluation and communication tools; stakeholder’s map.
Although societial impact is still not measurable, the implementation of social responsibility
in a public domain irradiation facility is possible and replicable. Principles and core subjects
are closely related and directly or indirectly contemplated in integrated safety, health, envi-
ronment management, quality and good irradiation practices, and contribute to increasing
cultures and consolidation of relationship with stakeholders.
312 IAEA–CN–241–108
PA1
Eid Session PA1, Wednesday 14:15 PA1-17
ESR Dosimetric Properties of Sodium Glutamate
S. E. Eid1
1National Center for Radiation Research and Technology (NCRRT), Nasr City, Cairo, Egypt
Corresponding Author: S. E. Eid, seif_dose@yahoo.com
Monosodium glutamate powder and rods (3 ˆ 10 mm) were studied to be a radiation
sensitive material for ESR dosimetry. Samples were irradiated with 60Co γ-rays. The
developed signal after irradiation increases with the increase of the monosodium glutamate
in the rods. The prepared powder can be used in the dose range from 10–90 kGy, whereas
the rods are useful in the range from 10–120 kGy. The obtained number of free radicals
per 100 ev (G value) was found to be 0.201 ˘ 0.01. The g factor is 2.0113 ˘ 0.0001. The
rods have the advantage of negligible humidity effects during irradiation. The pre- and
postirradiation stability was found to be satisfactory.
IAEA–CN–241–369 313
PA1
PA1-18 Session PA1, Wednesday 14:15 El-Motaium
Ionizing Radiation as a New Technique for Treating Sewage
Wastewater and Sludge in Arid Regions
R. El-Motaium1
1Egyptian Atomic Energy Authority (EAEA), Cairo, Egypt
Corresponding Author: R. El-Motaium, elmotaiumr@yahoo.com
The production of sewage water and sludge is continuously increasing as a result of popu-
lation growth and industrial expansion. Utilization of sewage water and sludge without
proper treatment can induce environmental pollution and human health problems. Treated
sewage water could be considered as a water resource and treated sludge could be used as
organic fertilizer and soil conditioner. This is particularly true in arid region, where water
scarcity is a major problem for agriculture and the lack of organic matter and nutrients is
the main feature of sandy soil. The reuse of treated sewage water and sludge can solve these
problems.
Sewage water and sludge contain several contaminants, e.g., pathogenic organisms, toxic
organic pollutants and heavy metals, high nitrate and high BOD & COD. The convention
methods of sewage water treatment (primary, secondary, tertiary) are not efficient in remov-
ing such contaminants. Sewage water and sludge were exposed to γ-radiation from 60Co
sources and electron beam from accelerators. Analysis of pathogenic organisms, heavy
metals and toxic organic pollutants, before and after irradiation, was performed according
to The Standard Methods for the Examination of Water and Wastewater.
Results indicated that ionizing radiation is an effective method in treating sewage water and
sludge. The potential effect of radiation includes pathogen disinfection, organic pollutants
degradation and soluble heavy metals reduction. The best radiation dose for pathogens
disinfection was 1 kGy and 6 kGy for sewage water and sludge, respectively. A reduction
in soluble heavy metals was observed in sewage water and sludge as a result of radiation
treatment. Degradation of toxic organic pollutants (PAH) in moist sludge reached 79% at
6 kGy γ-radiation dose. Irradiated sludge applied to sandy soil has increased crop yield,
improved soil fertility (organic matter and nutrients), improved soil physical and chemical
characteristics.
In conclusion, radiation treatment is recommended as an innovative and reliable method to
improve sewage water and sludge characteristics.
314 IAEA–CN–241–055
PA1
Farah Session PA1, Wednesday 14:15 PA1-19
EPR Characterization of a Medical Grade Polyethylene for High
Dose Dosimetry
K. Farah1, F. Hosni1
1National Center for Nuclear Sciences and Technologies (CNSTN), Sidi Thabet, Tunisia
Corresponding Author: K. Farah, kafarah@gmail.com
The quality control of radiation processing of polymers and composites by electron beam
(0.1–10 MeV), γ- and X-rays (0.6–7.5 MeV) can often be achieved by full knowledge of the
irradiation parameters and by periodic product analysis. In such cases where the product
itself is used for the quantitative control of process efficiency other radiation dosimeters
are not necessary. The main changes induced by irradiation on the polymer structure are
the creation of free radicals and the modification of the electronic configuration of these
materials. The electronic paramagnetic resonance of the ionizing radiation induced free
radicals in polyethylene has been extensively investigated by many authors. However, to the
best of our knowledge, there is no data in the available literature regarding EPR dosimetric
properties of the polyethylene.
In this work we are interested in the free radicals induced by γ and electron beam irradiation
in polyethylene in order to investigate its use as high-dose dosimeter.
The polyethylene samples were obtained from commercial medical-grade polyethylene
sheets of 28 µm thick which were cut into pieces of 30 ˆ 4 mm2 for EPR measurements.
The PE samples were subjected to different irradiation doses in air and in nitrogen at room
temperature by 60Co) γ-rays (5–118 kGy) and 2.2 MeV electrons beam (25–1000 kGy). The
EPRmeasurements were recorded at room temperature by means of an X-band Bruker EMX
machine with a microwave frequency of about 9.5 GHz.
The EPR spectrum obtained immediately after irradiation consists of six lines with a small
asymmetric component, the six-line spectrum is attributed to alkyl radicals (AR) and the
unbalanced line spectrum is attributed to the peroxide radical (PR). The effect of increasing
the dose of PE films was studied in the range 5–50 kGy. The intensity of the EPR spectra
increases with increasing dose. The dose response curve of AR follows a linear model, while
the evolution of the PR curve follows a first-order kinetics model. We observed a strong
decrease of ARs during the first three days after irradiation followed by a slow decrease
until their total disappearance after 9 days. The PR concentration increased significantly
after irradiation to stabilize after 31 days. The PRs thus formed are interesting for dosimetry
because they exist alone without overlapping with other radicals and are stable. However,
the very long stabilization time is a disadvantage. We found that the PR is completely
separable after annealing for 20 minutes at 100˝C. The repeatability of measurements for
the two radicals has been proven. The variation coefficients were found to be less than 1%.
IAEA–CN–241–044 315
PA1
PA1-20 Session PA1, Wednesday 14:15 Fulop
Treatment of Organic Pollutants Based on PCB in the River
Sediment by Electron Beam
M. Fulop1, A. Sagatova2, D. Siplak3, K. Conka1, P. Hybler1, and Ľ. Darážová2
1Slovak Medical University, Bratislava, Slovakia
2Slovak University of Technology in Bratislava, Bratislava, Slovakia
3EVPÚ a.s., Nová Dubnica, Slovakia
Corresponding Author: M. Fulop, marko.fulop@szu.sk
Polychlorinated biphenyls (PCBs) belong among the most persistent and bioaccumulative
substances. Long-term production of PCBs in the 20th century has resulted in excessive
concentrations of this organic pollutant in the environment with about 200 000 inhabitants
in eastern Slovakia. Different techniques for removing PCBs from sediments were evaluated,
but none of them has met three requirements of the local district authority: a) the PCB
degradation facility should be mobile and easily relocatable to other contaminated sites;
b) Techniques for PCB destruction should have negligible secondary waste generation, with
minimum catalysts, without PCB burning, and be easily automated; c) non-prohibitive
capital and operating costs.
The goals of the present work are to justify the method for electron beam degradation of
PCB (EBDPCB) in sediments, which so far has not yet been used industrially. To fulfil
the requirements of the local district authority the following methods were chosen: a) A
relocatable electron accelerator for in site EB processing in environment with shielding
corresponding to electron accelerator parameters and dimensions is considered; b) The
toxic equivalency factor was used to determine the toxic equivalent which determined the
clean up and remediation levels for the PCB mixture; c) Investment and operating costs
depend on the effectiveness of radiochemical reaction, design and technical parameters of
the electron irradiator.
The EBDPCB method demonstrated that ionizing radiation produced by high-energy elec-
tron beams is remarkably effective in transforming PCBs into less problematic species with
minimum catalysts. To increase the efficiency of radiochemical reaction of the EBDPCB,
chemical pretreatment of sediments by using various combinations of isopropanol, K2CO3
and CuSO4, have been tested. EBDPCB efficiency increased by using an electron energy of
3.6MeV compared to 5MeV. In comparison to other types, the accelerator based onDC trans-
former 50{60 Hz has an advantage in its reliability (availability), high average beam power
(productivity), electrical and beam utilization efficiency (operation cost), beam energy for
EBDPCB, transportable shielding and price (capital cost). Design of transportable DC trans-
former type 50{60 Hz electron accelerator for EBDPCB has been calculated by the Monte
Carlo code MCNPX for electron beam irradiators of 2.5 MeV/100 kW and 3.5 MeV/100 kW.
Themain source of PCB contamination in eastern Slovakia are sediments in Channel Strážske.
Among several methods for environment remediation, the method of radiation degradation
of PCBs in sediments by electron beam is the most appropriate for application at Channel
Strážske. The radiation degradation method for PCBs is environmentally friendly and the
irradiation facility with electron accelerator can be transported directly to the site of PCB
contamination. Treated sediments are recyclable as building gravel sand.
316 IAEA–CN–241–275
PA1
Furuta Session PA1, Wednesday 14:15 PA1-21
A New Fluorescence Detection Method with Plastic Scintillators
Using a Conventional LSC-Organic Waste Less Method
E. Furuta1, Y. Kato2, and S. Fujisawa2
1Ochanomizu University, Tokyo, Japan
2Hitach Ltd., Japan
Corresponding Author: E. Furuta, furuta.etsuko@ocha.ac.jp
For tracer experiments in life science field, many types of compound are labelled with
β-emitters. The β-emitters are generally measured using a liquid scintillation counter
(LSC) because of their low energies. An LSC is a superior machine with high counting
efficiency; however, there are two main demerits. Organic liquid wastes are generated after
measurement because the sample is dissolved in liquid organic scintillator, and a spectra
quenching arises, erasing the identities of the kind of nuclides in a sample. We developed
a new fluorescence detection method with plastic scintillators, an alternative material to
liquid scintillator, using a conventional LSC without generation of organic liquid waste.
Two kinds of plastic scintillator (PS) were prepared; a sheet type (BC-400; Saint Gobain
USA) and a pellet type (EJ-200; G-tech Japan). The sheet was 0.5 mm in thickness and
was cut 55 mm in length (max. 75 mm) and 20 mm in width (max. 30 mm) for a 100 m`
Teflon vial of inner diameter 33 mm (Sanplatec Co. Japan) used for nonvolatile compounds.
The pellet was a 3 mm cylindrical shape and approximately 90 g of pellets were put in
the Teflon vial, which were used for volatile compounds. The LSC used was LSC LB-7
(Hitachi, Ltd. Japan). Radioactive materials used (Moravek Biochemicals Inc. USA) were
3H-methionine, 14C-arginine and 35S-methionine as nonvolatile compounds and tritiated
water and 14C-acetic acid sodium salt as volatile compounds. Additionally, the surface of
the PS-sheet was treated with dielectric barrier discharge plasma or fluorine gas treatment
for tritium compounds measurement, because the surface was changed hydrophilicity and
the contact area with the sample solution was extremely widened. Quantitative analysis
and detection limits for using both sheets and pellets were studied.
The counting efficiency using the PS-sheets was same as that of liquid scintillator use, when
the surface of PS-sheets were treated with plasma for tritium measurement. Though the
PS-pellets showed higher counting efficiency compared with that of liquid scintillator when
the sample solution was less than 500 µ`, the counting efficiency was decreased depending
on the sample solution increased. However, the detection limit became low with large
sample solution.
Quantitative and qualitative analysis of β-emitters were possible using plastic scintilla-
tors without generating of liquid organic waste. The PS-pellets and sheets could be used
repeatedly after rinsing under hot running water. These PS-methods are low load and
eco-friendly.
IAEA–CN–241–016 317
PA1
PA1-22 Session PA1, Wednesday 14:15 Gao
Optimal Design of 60Co Single Source Radiation Facility with
Monte Carlo Method
F. Gao1
1China Institute of Atomic Energy (CIAE), Beijing 102413, People’s Republic of China
Corresponding Author: F. Gao, 13661149977@163.com
A reference radiation field is necessary for the calibration of radiation dose monitoring
meters, and 60Co single source radiation facilities are an important resource to produce this
reference radiation field. Uniformity and scattered photons are the most important criteria
for reference radiation field. The Monte Carlo method was used to calculate the uniformity
and scattered radiation of the reference radiation field which was produced by 60Co single
source radiation facility. A close-to-reality simulation model of the facility was used to
calculate scattered air-kerma along the whole range of the source-detector-distance (SDD)
along the central beam and air-kerma off-axis beam profiles at 1 m source-detector-distance
(SDD). Other characteristics such as the individual contributions of photons scattered in
collimator, floor, walls, mobile platform and other parts of the radiation halls to the total
air kerma rate on the beam axis were calculated. Optimal design of 60Co single source
radiation facility was accomplished according to the simulation results. A PTW ionization
chamber was used to measure the radiation field produced by 60Co single source radiation
facility, measured results show that the scattered radiation and uniformity of the radiation
field are in good agreement with the simulation results. The total scattered contribution
is less than 4.0%, and falls below the ISO 4037-1 requirement of a maximum scatter of 5%.
The 60Co single source radiation facility performances meet the design requirements.
318 IAEA–CN–241–101
PA1
George Session PA1, Wednesday 14:15 PA1-23
Conceptual Development of an Irradiator for Cross-Linking of
Cables Using 60Co γ-Rays
J. R. George1, K. S. S. Sarma1, A. K. Kohli1, and B. K. Pathak1
1Board of Radiation & Isotope Technology, Department of Atomic Energy, Mumbai 400 001, India
Corresponding Author: J. R. George, jrgeorge@britatom.gov.in
Cross-linking provides significant commercial benefits towire and cable insulation. Ionizing
energy is an efficient means of cross-linking the polymers to improve many cable properties
including insulation. In this process chemical bonds are formed between layers of polymer
molecule to produce three-dimensional insoluble network. The present methods of cross-
linking are thermal, chemical, or EB from accelerators. EB cross-linking is the latest and
improves properties like fire resistance, flame properties, abrasion resistance, stress crack
resistance, etc., however, there is a limitation of EB penetration in large diameter cables
(ą 30 mm diameter) restricting its application. Therefore, the feasibility of processing
multicore cables of large diameters with γ-rays was explored. The insulation jacketing of
multicore cables are made of PVC or PE. The dosimetric aspects were studied for a cable
irradiator design which has been made in such a way that the cable will move through
a pipe housed in γ-irradiation cells (GICs) each of which have 60Co source pencils (BRIT
made BC-188) of 7.4 PBq arranged around the pipe in a suitable diameter (PCD). The pipe
can accommodate cables of diameters up to 72 mm. The cells have effective irradiation
lengths („ 1 m) and lead shielding of adequate thickness. The objective of the study was to
evaluate the dose profile in cables when irradiated in a γ-irradiation cell and to optimize
the PCD of source pencil arrangement to get the appropriate dose uniformity ratio with the
specified target dose of 100 kGy and to arrive at number of irradiation cells required for a
suitable through-put. Based on the results of the study a γ-irradiator with multiple number
of irradiation cells is under development in BRIT, a unit of the Department of Atomic Energy,
India.
IAEA–CN–241–166 319
PA1
PA1-24 Session PA1, Wednesday 14:15 Gomes
Assessment of Safety Systems Design of Industrial Irradiation
Facilities in Brazil
R. Gomes1, J. D. R. Lopes Gomes1, M. L. Costa1, Z. Thomé2, and E. L. Costa1
1Brazilian Nuclear Energy Commission (CNEN), Rio de Janeiro, Brazil
2Instituto Militar de Engenharia, Rio de Janeiro, Brazil
Corresponding Author: R. Gomes, rogeriog@cnen.gov.br
Accidents occurring in irradiation facilities have demonstrated that these facilities have
safety-critical systems, which should be designed to meet proper safety requirements. The
IAEA’s publication SSG 8 provide specific and practical recommendations on the safe design
and operation of irradiations facilities, for use by operating organizations, the designers of
these facilities and by regulatory bodies. The first industrial irradiation facility in operation
in Brazil was designed in the ’70s. Since then, minor modifications and upgrades, as
sensors replacement, have been introduced in order to reduce the technological gap in the
control and safety systems, however, in the case of safety systems in irradiation facilities,
the requirements concerning safety and reliability are of ultimate importance. This work
evaluates the adequacy of existing safety systems and their sensors at Brazilian irradiation
facilities, taking into account the recommended IAEA’s design requirements.
The study is based on an assessment of the licencing process of irradiation facilities, as
well as the experience of regulatory inspections in these facilities. It was also taken into
account the knowledge, concepts and solutions developed to upgrade existing safety system
in facilities throughout the world. Irradiation facilities can be defined on the basis of its
design and, in particular, the accessibility and shielding of the radioactive source. The Brazil
facilities can be categorized into 9 panoramic γ irradiators (4 dry and 5 wet storage) and
4 panoramic irradiation facilities using generators.
Notable findings arising from this study include: a) Some sensors are not interlocked with
the irradiator central controls unit, thus they not act automatically when a predetermined
value is exceeded, this condition is normally observed, basically, on the radiation monitor
of the water treatment system and on the fire protection system; b) In older irradiators the
seismic detector is not installed; c) Redundant systems in the personnel access door can be
improved, using pressure mats combined with optoelectronic barriers.
Additionally, it was considered if the irradiation facility can be operated only if all safety
systems are in place and functioning. It was carried out a diagnosis of the “state of the
art” of safety systems of Brazilian industrial irradiators, taking into account the national
regulations and the latest IAEA´s recommendations.
Some sensors of safety systems in oldest Brazilian irradiators can be improved, basically
for automatic actuation, thus the upgrade of control systems in irradiator facilities would
use the advances in computer technology, old control units based on relay logic should be
replaced with a new one based on redundant programmable logic controllers, however, it
should be emphasized that the operating organization should obtain the approval of the
regulatory authority before implementing any modifications on the irradiator that may have
significant implications for radiation protection.
320 IAEA–CN–241–315
PA1
Goswami Session PA1, Wednesday 14:15 PA1-25
Measurement of Residence Time Distribution of Wastewater in a
Constructed Wetland System Using Radiotracer Technique
S. Goswami1, J. S. Samantray1, D. Poswal2, H. J. Pant1, S. R. Asolekar2, and A. Dash1
1Isotope Production and Applications Division (IPAD), Bhabha Atomic Research Centre (BARC), Mumbai, India
2Centre for Environment Science and Engineering, Indian Institute of Technology, Mumbai-400076
Corresponding Author: S. Goswami, gsunil@barc.gov.in
Constructed wetlands (CW) are human engineered systems that utilize natural process for
treatment of wastewater. They have been highly applicable in developing countries, due
to their characteristics like utilization of natural processes, simple construction, operation
and maintenance, process stability, and cost effectiveness. The design of constructed wet-
land requires multidisciplinary inputs involving biological and ecological sciences, aquatic
chemistry, engineering hydrology and flow hydrodynamics. The CW are heterogeneous in
nature. Thus, they are prone to show deviation in the designed flow pattern and residence
time for the treatment of wastewater. The aim of the present study is to measure mean
residence time (MRT) and flow patterns of CWs using radiotracer technique.
The wetland is 13.0 m long, 3.0 m wide and 0.7 m deep. The geometric volume of the
system is 27.3 m3. The system walls and bottom were lined to prevent leakage. The wetland
has slope of 1% at the bottom and an average porosity of 52%. About 100 MBq of 99mTc
(half-life τ1{2 “ 6.6 h, γ energy 139 KeV) as sodium pertechnatate was used in each run. The
radiotracer concentrations monitored at different planes across the width and outlet using
NaI(Tl) scintillation detectors were connected to a computer controlled data acquisition
system (DAS), itself set to record tracer concentration once per minute at the outlet and
across the bed of the system.
The RTD data was treated and analyzed using a RTD analysis software. The data treatment
includes background subtraction, tail correction, radioactive decay correction, zero shifting,
smoothing and normalization. The data was used to calculate MRT, dead volume of system
and hydraulic efficiency of the plant. A four-parameter model, i.e., tank in series exchanging
with dead volume model prefixed with plug flow component, was used to simulate the
RTD data.
The radiotracer experiments were successfully conducted in an artificially constructed wet-
land system and mean residence times and dead volumes were determined at different
operating conditions. No bypassing or short-circuiting was observed in the CW. The pro-
posed four-parameter model was found suitable to describe hydrodynamics of wastewater
in the wetland. The hydrodynamic parameters indicate that the CW works efficiently at a
bed height of 0.6m,wastewater flow rate 2.3m3{s andwith a two point distributor geometry.
However, the results of the study also indicate that on increasing the number of injection
points, the efficiency of the CW will increase.
IAEA–CN–241–321 321
PA1
PA1-26 Session PA1, Wednesday 14:15 Gryczka
Application of Low Energy Electron Beam in Microbiological
Decontamination Process
U. Gryczka1, W. Migdał1, S. Bulka1, and D. Chmielewska-Śmietanko1
1Institute of Nuclear Chemistry and Technology (INCT), Warsaw, Poland
Corresponding Author: U. Gryczka, u.gryczka@ichtj.waw.pl
Food preservation with ionizing radiation has about 100 years of history. To date, more than
fifty countries have given approval for over sixty products to be irradiated. Themost popular
application uses γ-irradiators. Increasing interest is also observed for the application of
high energy electrons as well as X-rays. New trends in the application of this technology is
related to the use of low energy electron beam, characterized by limited penetration depth.
In the process with the use of high energy electrons, the whole food volume is irradiated.
Since microorganism reside mostly on the surface of dry food, irradiation of the external
layer should be sufficient to eliminate food-bornemicroorganisms. Additionally, operational
safety issues are relevant, since low-energy EB machines are equipped with local compact
shielding and can be installed along with other industrial machinery in the same room.
This study concentrates on the determination of microbiological decontamination process
efficiencywith the use of an EB of energy between 100 and 300 keV. Two electron accelerators
installed in INCT were be used in the experiments. Elektronika (10 MeV, 10 kW) was used
for irradiation with high energy electrons. Accelerator ILU-6 is a resonant type machine
whose nominal beam operating range covers energies from 600 keV to 2 MeV. Low electron
energy was achieved by reducing the accelerating RF voltage. For the need of this study, the
modification of the pulse power supply system, electron gun arrangement and accelerator
beam sweep system of ILU-6 was made to lower the energy of emitted electrons to below
300 keV. The energy of the resulting beam was controlled using B3 dosimetric film stacks.
In the experiments, the microbiological load reduction was tested for food products, irradi-
ated with doses from 1 to 10 kGy. Selected samples of spices, dries herbs and seasonings
with different density and porosity were tested to control the total amount of aerobic bacteria
and mold. The relationship between dose of radiation for different energies of electrons
and effectiveness of the process was established. The effects of irradiation with low energy
electrons were compared with effects for high energy electrons.
The work was supported by Polish Ministry of Science and Higher Education under the
project “Investigation on application of low energy electron beam for microbiological control
of food and agricultural products” and by the IAEA under the Coordinated Research Project
D61024.
322 IAEA–CN–241–195
PA1
Ihsan Session PA1, Wednesday 14:15 PA1-27
Core Neutronic and Source Strength Analyses of 60Co
Production in Local Power Reactors
A. Ihsan1, M. K. Chughtai1
1Pakistan Atomic Energy Commission (PAEC), Islamabad, Pakistan
Corresponding Author: A. Ihsan, ihsanaamir@gmail.com
A detailed analytical study on the feasibility of local production of 60Co in power reactors
of Pakistan, C-1 & C-2 (Chashma Nuclear Power Plant, unit-1/unit-2, PWR type), has been
made by irradiating metallic pencils of 59Co in-core and out-of-core locations. In the first
scheme, four fresh fuel assemblies with four guide tube locations per fuel assembly have
been selected for in-core 59Co loading. A total of about 150 kCi of 60Co have been produced
in these locations over a period of one fuel cycle („ 385 days). Detailed neutronic analysis
of C-1/C-2 core was carried out in order to determine the effect of sample irradiation upon
core performance at full power. The reactivity calculations show that fuel cycle length would
be slightly shortened, approximately by one day, without affecting the safety parameters
due to 59Co loading at in-core locations. The estimated specific activity of a cobalt pencil at
the end of one year is 19.25 Ci/g.
Alternatively, in C-1 & C-2 reactors, the four out-of-core vacant locations on the outer surface
of the reactor core barrel, which were earlier occupied by the now-withdrawn surveillance
capsules assemblies (SCAs), have been selected for 60Co production. In this scheme four
bundles in the form of stainless steel tubes, each tube containing 18 concentric cobalt pencils,
would be loaded in the SCA hanger assemblies. An estimated 30 kCi of 60Co are produced
in these locations over two core cycles („ 770 days). Since cobalt targets are placed in the
same ex-core locations that earlier contained the stainless steel and other RPV material
samples in SCAs, the cobalt loading would have no impact on nuclear reactor safety. In
order to determine the effect of 59Co irradiation upon core reactivity, a detailed neutronic
analysis of the C-1/C-2 core was also carried out at full power. The core design calculations
show that there is no significant effect on critical core parameters and reactor operation, and
fuel cycle length is not reduced. The calculations show that the estimated specific activity
of capsule at the end of two years is 0.83 Ci/g at the cobalt loaded SCA location. For a total
mass of 35 kg in 72 59Co samples, the total activity from the production of 60Co is estimated
to be 30 kCi. Detailed shielding analysis and dose rates of irradiated 60Co pencils have also
been carried out. Thicknesses of shielding materials have been optimized based on the
surface dose rate criteria of ď 2 mSv/h. Based on these analyses, the cylindrical shielded
transport containers with different loading combinations have also been designed for safe
transportation.
From these analyses, feasibility of 60Co production at the in-core and out-of-core vacant
locations of SCAs in the power reactor has been demonstrated without any major modifica-
tion in reactor core or imposing any serious impact on reactor core performance and plant
safety.
IAEA–CN–241–234 323
PA1
PA1-28 Session PA1, Wednesday 14:15 Jang
RI-Biomics Technology for the Advance Radioisotope
Application in Modern Life
B. S. Jang1, S. H. Park1
1Advanced Radiation Technology Research Institute (ARTRI),
Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
Corresponding Author: B. S. Jang, jangbs@kaeri.re.kr
The RI-Biomics Center opened at ARTRI in the fall of 2013, and is a facility dedicated to
improving the quality of life by developing advanced radioisotope applications in domains
from basic biological sciences to the pharmaceutical industry. The RI-Biomics Center
supports the research interests of a wide range of investigators from multiple disciplines,
including academic biomedical sciences and the pharmaceutical industry, to elucidate the
phenomena of life and evaluate the pharmacokinetics of drug candidates and medical
bio-materials. We designed, build, and have put into routine use a radioisotope based
total analysis system to handle the needs of a wide range of experiments from classic
3H, 14C based pharmacokinetic studies to small-animal molecular imaging studies using
micro-SPECT/CT/PET, 7.0 T small-animal MRI, fluorescence optical imaging devices and
autoradiography, etc.
The centre was designated as an Advanced Research Center for Nuclear Excellence in
2012 for development of RI-Biomics Bio-sensing application technology such as evaluation
technology of life phenomena using 3D-ADMET(3-dimensional absorption, distribution,
metabolism, excretion, toxicity study as advanced pharmacokinetic research), development
of high value drug/functional food/medical devices or materials as well as advanced tech-
nology including GLP-like non-clinical study for the contribution on the improving quality
of human life. The goal of RI-Biomics technology is to contribute to the peaceful applica-
tion of radiation and radioisotopes through the development of advanced technologies for
enhancing understand life phenomena. In pursuit of this goal our research focusses on the
development of new technologies such as: a) SPECT/PET based 3D-ADMET study and clas-
sic 14C/3H based ADME study for support the pharmacokinetic information of new drug
or toxicant from small synthetic chemicals to big biologics such as antibody, biomolecules,
nano-materials and polymers); b) Radioisotope based biosynthesis of high value herbal
resources used to alternative medicine to support the advanced evaluation for traditional
medicines; c) Study of radiation effects on the living organisms such as microorganisms,
cells, plant and experimental animals such as fishes and rodents; and d) Development of ex-
perimental systems for the study of radiation or radioisotope application such as screening
the highly radiation-sensitive experimental animals, etc.
In addition, we are involving the professional and public education systems with the
University of Science and Technology (UST), Korea Association for Radiation Application
(KARA) andNational Research Foundation of Korea (NRF), etc., to contribute the enhancing
public acceptance for radiation. In the future, we will start a programme sharing the effects
of radiation on living organism and environment to enhancing the public acceptance of
nuclear & radiation technology. After the Fukushima Daiichi nuclear disaster the public
were seized with fear surrounding nuclear and radiation application. Currently we propose
convergence research to enhance the public acceptance.
324 IAEA–CN–241–377
PA1
Jung Session PA1, Wednesday 14:15 PA1-29
Effect of γ-Ray and Electron Beam Irradiation on Reduction of
Graphene Oxide Suspension in Aqueous Alcoholic Solution
C.-H. Jung1, S. Yu1, J.-Y. Sohn1, J. Shin1, and I.-T. Hwang1
1Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
Corresponding Author: C.-H. Jung, jch@kaeri.re.kr
Enormous scientific and technological progress has been in graphene applications, since its
unique properties were unearthed by Andre Geim and Konstantin Novoselov in 2004. To
realize the commercialization of graphene, the cost-effective and scalable production has
been of great important and still considered as one of key issues in the graphene community.
In this context, the wet chemical method based on the reduction of graphene oxide (GO) has
been the most popular way to produce graphene because it probably offers large scalability
and production of solution-processable graphene that can facilitate its many applications.
Thus, numerous chemical-, heat-, and light-based reduction strategies has been exploited.
However, these strategies have drawbacks such as a necessity of toxic and explosive reducing
agents, high temperature processing, and less scalability. Hence, there still is a high demand
for the development of a cost-effective and large-scale method.
This research investigated the reduction of GO suspension in aqueous ethanol (EtOH)
through γ-ray or electron beam (EB) irradiation with the advantages of no need of reducing
agent, room-temperature processing, and mass-producibility. For radiation-reduction of
GO, a solution of GO suspension in 50 v/v% EtOH/water prepared by diluting a 5 mg/ml
GO solution in H2O was added to a glass vial, sealed with a rubber septum, and purged
with nitrogen gas. The resulting vials containing the GO suspension were irradiated at
room temperature by γ-rays from a 60Co source or EB from a 10 MeV UELV-10-10S electron
accelerator located at KAERI, at various absorbed doses ranging from 50–100 kGy. The
dose rate for γ-ray irradiation was 10 kGy and the scan rate for the EB irradiation was
10 kGy/min. The resulting reduced GOs (rGO) were systematically characterized in terms
of optical, chemical, thermal, morphological and electrical properties.
From the results of UV-Vis, FT-IR, TGA, and TEM analyses, it is clearly confirmed that
GO suspension in aqueous EtOH was effectively reduced by γ-ray and EB irradiation, and
the thermal, chemical, and thermal properties of the resulting rGO was dependent on the
absorbed dose. Noticeably, based on the electrical conductivity measurements, the rGO
prepared by the EB irradiation exhibited similar magnitude of the electrical conductivity to
that prepared by the γ-ray irradiation at the same absorbed dose, indicating that the EB
irradiation can reduce GO more quickly than the γ-ray irradiation.
In conclusion, the reduction of GO suspension in aqueous EtOH can be successfully achieved
by both γ-ray and EB-irradiation. More importantly, EB-based reduction is much faster than
γ-ray irradiation. Therefore, this EB-irradiation reduction is promising for the cost-effective
and large-scalable production of graphene.
IAEA–CN–241–259 Presenter: S. Yu 325
PA1
PA1-30 Session PA1, Wednesday 14:15 Kang
Radiation Shielding Analyses of a 10 MeV LINAC for Electron
Beam and X-Ray at KACST
W.-G. Kang1, S. Pyo1, T. Alkhuraiji2, B. Han1, and C. Kang1
1EB TECH Co., Ltd., Republic of Korea
2King AbdulAziz City for Science & Technology (KACST), Riyadh 12371, Saudi Arabia
Corresponding Author: W.-G. Kang, unikang@eb-tech.com
The King AbdulAziz City for Science & Technology (KACST) in the Kingdom of Saudi
Arabia plans to build a 10 MeV, 15 kW LINAC for electron beam and X-ray applications. The
design and construction of the accelerator building will be conducted with the cooperation
of KACST and EB Tech Co., Ltd. This report presents the shielding analysis of the accelerator
building using the MCNP Monte Carlo radiation transport code. In order to improve the
accuracy in estimating deep radiation penetration and to reduce computation time, several
variance reduction techniques, including the weight window (WW) method, DXTRAN
spheres were considered. Radiation levels were estimated at selected locations in the
shielding facility running MCNP6 for particle histories up to 1.0ˆ 108. The final results
indicated that the calculated doses at all selected detector locationsmet the dose requirement
of 50 mSv/yr, which is the U.S. NRC requirement.
326 IAEA–CN–241–146
PA1
Karakirova Session PA1, Wednesday 14:15 PA1-31
Optimizing the Size and Composition of Solid State/EPR
Dosimeters
Y. Karakirova1, N. Yordanov1
1Bulgarian Academy of Sciences, Sofia, Bulgaria
Corresponding Author: Y. Karakirova, daniepr@ic.bas.bg
In the last few decades, the alanine/ Electron paramagnetic resonance (EPR) dosimetric
system has been accepted by the IAEA as a secondary (transferring type) dosimetric system.
In order to increase the sensitivity of the solid state/EPR (SS/EPR) system, several new
materials have been studied. Sucrose has been studied for a long time as a dosimeter in
radiation accidents and in high-dose dosimetry by using different analytical techniques. In
parallel, optimization of the shape and size of the dosimeters may increase the sensitivity of
the system.
In the current study, an attempt to improve the sensitivity of SS/EPR dosimetry is made. In
view of this, cylindrical dosimeters of different diameters, both in presence and absence of
internal standard Mn/MgO2, have been prepared and tested. Sucrose and alanine were
used as radiation sensitive materials in the dosimeters. The influence of the diameter of
cylindrical dosimeters on the EPR response was studied at 1 mW microwave power and
0.2 mT modulation amplitude, in other to avoid some interference of the instrumental
parameters. In the absence of Mn in MgO2, the EPR signal intensity increased with larger
dosimeter diameter at equal doses, a normal effect given the increase in material. In the sam-
ples composing internal standard the ratio of the EPR intensity of the signal (Is) to intensity
of the manganese standard (IMn) is used. In this case the EPR response is independent of
the dosimeter diameters.
The effect of size and composition of dosimeters used in SS/EPR dosimetry on their response
also is studied. It has been found that in the absence of internal standardMn/MgO2, the EPR
intensity increased linearly with the absorbed dose up to 20 kGy, after which it is saturated.
In dosimeter diameter dependence, the slope is different. It is biggest in case of 3 and
4 mm diameter. Further increase of the diameter of the dosimeters is not recommended
since the increased penetration of the dosimetric material into the electric component of
the microwave field in the EPR cavity decreases the EPR response. In presence of internal
standard (Mn/MgO2) into the dosimeter (so-called self-calibrated dosimeter) the EPR signal
intensity increased linearly with the dose in the all investigation region of dose (3–80 kGy).
It can be concluded that the best results give self-calibrated cylindrical dosimeters.
IAEA–CN–241–050 327
PA1
PA1-32 Session PA1, Wednesday 14:15 Kim
Degradation Characteristics and Transformation Products of
Iodinated Contrast Media Using Ionizing Radiation
H. Y. Kim1, T.-H. Kim1, K. Lee1, S. M. Cha1, B. Shim1, J. I. Kim1, and S. Yu1
1Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
Corresponding Author: H. Y. Kim, hykim33@kaeri.re.kr
In the present study, the degradation of iodinated X-ray contrast media (ICMs) using ioniz-
ing radiation was investigated. ICMs (radiocontrast agents containing iodine for enhanced
visibility of vascular structure and organs) are a widely used diagnostic pharmaceutical
compounds. ICMs are considered as persistent pollutants in the watershed due to con-
tinuous release into aqueous ecosystem and low degradation efficiency in conventional
treatment processes. Therefore, various advanced oxidation processes (AOPs) have been
currently applied to treat non-degradable pharmaceuticals including ICMs. Radiolysis is a
new treatment technology to eliminate a variety of non-degradable compounds, showing
higher degradation efficiency. Although studies considering degradation of non-degradable
compounds with AOPs have been increased, there has been insufficient information of
byproducts produced by the treatment, especially ionizing radiation. Therefore, the aim
of this study was to evaluate the degradation characteristics of ionizing radiation treated
ICMs, and to identify the radiolytic transformation products.
The target compounds were treated using ionizing radiation, with the absorbance doses
from 0.1 to 5 kGy (1 kGy “1 kJ{kg). Ionizing radiation was achieved using a high level
60Co source at KAERI. LC-QTOF-MS (Agilent Technologies, USA) and LC/ESI-MS/MS
(Agilent Technologies, USA) were used for qualification and quantification analysis of
degradation byproducts. To confirm that the byproducts of irradiated ICMs originated
from the radiolysis, the variation of parent compounds in dark control was estimated.
There was no relevant change of target compounds in dark control for 40 days, indicat-
ing that hydrolysis of target compounds were negligible. Target compounds were rapidly
declined with absorbance doses, showing the rate constants (kr) of 1.7299 kGy´1 (iover-
sol), 1.5485 kGy´1 (iohexol), 1.3745 kGy´1 (iopromide), 1.3522 kGy´1 (diatrizoate), and
1.2726 kGy´1 (iopamidol) (r2 ą 0.99). Degradation of ICMs led to sequential release of
iodide, indicating that reductive deiodination is one of the major degradation mechanism of
ICMs. Deiodinated degradation byproducts of iopromide including TP665 (C18H25I2N3O8),
TP540 (C18H26IN3O8), TP414 (C18H27N3O8) were also detected in qualification analysis.
328 Presenter: S. Yu IAEA–CN–241–085
PA1
Ladjouzi Session PA1, Wednesday 14:15 PA1-33
Structural Characterization of γ Irradiated GdBO3/Silica
Composite Obtained by Sol Gel Process
S. Ladjouzi1, R. Tala-Eghil2, M. Izerrouken1, S. Hadji1, and L. Guerbous3
1Centre de Recherche Nucléaire d’Draria (CRND), Draria, Algeria
2M’Hamed Bouguerra University of Boumerdés, Boumerdès, Algeria
3Centre de Recherche Nucléaire d’Alger (CRNA), Alger-Gare, Algeria
Corresponding Author: S. Ladjouzi, ladjouzi_s@yahoo.fr
Samples of GdBO3/Silica composite were prepared by the sol gel process. After elaboration,
the samples were irradiated at room temperature with γ-rays using a 60Co radioisotope
source in the dose range from 1 to 5 kGy. The irradiation effects on the structural properties
of the synthesized powders were investigated before and after γ-irradiation using several
techniques. DSC analysis reveals that the characteristic temperature of crystallization (Tc)
increases as γ dose increases up to 2 kGy and, then, decreases with γ-ray dose up to 5 kGy
but remains higher than the temperature reached by an un-irradiated sample. XRD and
TEM results reveal that γ-ray irradiation reduces the crystallite size from 55 nm to 30 nm.
Moreover, it is found from the FTIR study that the absorption bands intensity assigned to
structural groups containing BO4 and BO3 units as well as the banding of Si–O–Si bond
increases with γ-ray dose up to 5 kGy. From these results, it is concluded that the γ-ray
irradiation up to a dose of 5 kGy improves the structural properties of the synthesized
material.
IAEA–CN–241–140 329
PA1
PA1-34 Session PA1, Wednesday 14:15 Lay
Research on Conversion of Natural Wastes to Useful Products by
Application of Radiation Processing for Agricultural Sector of
Myanmar
K. K. Lay1
1Department of Nuclear Engineering, Mandalay Technological University, Mandalay, Myanmar
Corresponding Author: K. K. Lay, khinlayster@gmail.com
Myanmar is an agricultural-based country and its economic development depends mainly
on agricultural sector productivity. People are trying to improve the productivity by using
a variety of fertilizers. Some kinds of fertilizers cause a decline of soil fertility and leave
fertilizer traces in food, thus are the main problems for our country. Moreover, average
temperature of our country is increasing yearly due to global warning, which is challenging
for our agricultural sector since water is essential for agricultural sector.
Radiation technology can be used to produce useful products to solve these problems and
themain aim of the research is to produce plant growth promoter and super water absorbent
material (SWA) from natural wastes by application of γ-radiation. Myanmar has many
streams and rivers as well as coconut trees in all part of country. Therefore, natural wastes
such as prawn shell and coconut (coin dust) shell were used as raw materials. The first step
for the production of irradiated chitosan (plant growth promoter) is a deproteinization and
deminerization processes. Effects of sodium hydroxide concentration and temperature on
the deproteinization process and the effect of hydrochloric acid concentration at ambient
temperature on the deminerization process were studied. Characteristics of products are
determined by Fourier transformed infrared spectroscopy (FT-IR). The best chitin was
used for the production process of chitosan in which different radiation dose and different
concentration of sodium hydroxide were applied to obtain optimum condition for the
deacetylation process. The degree of deacetylation (DD) was determined by band ratio
method of FT-IR spectra. It was found that the degree of deacetylation (DD) of chitosan
decreased with increase of radiation dose. Coir dust cellulose was produced from coin
dust shell by using soda process in which various concentration of sodium hydroxide and
various temperatures were used to determine the best cellulose. The resulting cellulose was
applied for SWA production by using potassium hydroxide, acrylic acid and γ-radiation.
Effects of acrylic acid concentration and radiation dose on SWA production were studied
and determinations of their characteristics were done. The characteristics of the cellulose
and SWAwere determined by scanning electronmicroscope (SEM) and FT-IR. It was noticed
that useful properties of SWA increased with radiation dose.
Production of useful products such as plant growth promoter and SWA for the agricultural
sector were studied in the research. Field or pot test of the two products will be studied. It
can be concluded that the research is effective not only for agricultural sector but also for
environmental monitoring since raw materials used in the research were natural wastes.
330 IAEA–CN–241–071
PA1
Liu Session PA1, Wednesday 14:15 PA1-35
Dose Increase System in a γ-Irradiator
G. Liu1, Q. Wu1
1BINE High-Tech Co., Ltd., People’s Republic of China
Corresponding Author: G. Liu, liuge@bineht.com.cn
In China, many γ-irradiator users encounter a problem, i.e., the product kinds are various,
but each product quantity is small. The absorbed-dose for each kind of product is usually
different. When processing these products, the user has to wait for the completion of one
product kind, the emptying of the source pass mechanism, changes to the master time,
and only then start to irradiate another kind of product. This causes the throughput and
source efficiency to be lower. To solve this problem, in the new BFT-type γ-irradiators in
China, we have designed a dose increase system. This system includes joint roller, stopper,
barcode reader etc., which is set inside the maze. Barcodes are attached on all totes. For
different products, the master time is set according to the absorbed dose common divisor.
For example, there are three kinds of product whose absorbed doses are 10 kGy, 15 kGy and
25 kGy. In order to process them at the same time, the master time can be set to make one
cycle of irradiation to reach 5 kGy. So the totes loading these products should be irradiated
for 2, 3 and 5 cycles, which are related to their barcodes. During the irradiation, when a
tote is conveyed to the outlet of the maze, the barcode reader will send its barcode to the
control system. The control system will decide the next motion by the tote’s total cycles and
its finished cycles: if the finished cycles are less than the total cycles, the tote will be moved
to the joint roller and be conveyed back to the radiation room; if the finished cycles equal to
the total cycles, the tote will be moved to the unloading station. The dose increase system
has been applied in many BFT type γ-irradiators. The result shows that the system solves
the problem of dealing with many kinds of small batch products. The system improves the
throughput and source efficiency greatly.
IAEA–CN–241–159 331
PA1
PA1-36 Session PA1, Wednesday 14:15 Lwin
Human Resource Development for the Application of
Radioisotope Techniques to Industry in Myanmar
K. Y. Lwin1, M. P. Hlaing1
1Department of Atomic Energy (DAE), Nay Pyi Taw, Myanmar
Corresponding Author: K. Y. Lwin, ms.khinyelwin@gmail.com
Competent and efficient manpower is one of the main sectors for the application of radiation
science and technology. The Department of Atomic Energy (DAE) has been conducting
E&T and R&D in the nuclear application field, cooperating with local institutions and inter-
national societies. Two technological universities have been offering academic programmes
for nuclear engineering (B.Tech, B.E., M.E. and Ph.D.) under the supervision of DAE.
To provide professional development, skill development and to have opportunities for
career advancement and future job prospects, a human resource development programme
in radioisotope techniques for application in industry has being carried out through national
TC project cooperating with IAEA since 2012. The Radioisotope Techniques Laboratory was
established under the DAE to transfer technology and implement radioisotope techniques
into practice.
The basic theory of γ-ray transmission, γ-column scanning and γ-computed tomography
techniques were introduced to students. The simulation of γ-column scanning is conducted
by using model of distillation column made of iron. Two computed tomography system,
GORBIT first generation CT system supported by IAEA and field-used BATAN CT system
provide by BATAN, Indonesia, are used to practice the computed tomography technique. To
conduct experiments in the radiotracer technique, an in-house pipe line system and water
flow-rig for simulation of chemical reactors provided by IAEA are used as compact and
useful tools.
Each of the tools has been adopted to the specific need of the country to achieve desired
HRD results and to assist individuals in learningmore effectively with the goal of improving
performance. From the development of industry-driven education and training programmes,
students can develop designs and software adaptable for need in the application to local
industries.
332 IAEA–CN–241–035
PA1
Madureira Session PA1, Wednesday 14:15 PA1-37
Application of Ionizing Radiation for Treatment and
Valorization of Cork Wasterwater
J. Madureira1, A. Pimenta1, R. Melo1, F. Margaça1, and S. Cabo Verde1
1Instituto Superior Técnico (IST), Lisbon, Portugal
Corresponding Author: J. Madureira, joanamadureira@ctn.tecnico.ulisboa.pt
The wastewater produced from the cork industry has a high concentration of undesirable
cork extracts such as phenolic acids, tannins and 2,4,6-trichloroanisol. These compounds
are difficult to degrade by conventional treatments, which make this water a toxic and recal-
citrant effluent that constitute a risk for the ecosystem and thus requires treatment before
being discharged into the environment. This work represents a comprehensive study of the
use of γ-radiation as an advanced oxidation process for wastewater treatment. This work
was carried out aiming to degrade recalcitrant compounds, although it was also assessed
the potential valorization of the cork industry wastewater through the selected recovery of
the valued antioxidants. The irradiations were performed at room temperature in a 60Co
chamber at the absorbed doses: 20, 50 and 100 kGy and dose rate range of 1.6–2.4 kGy{h.
Parameters of pH, COD, BOD and TSS were determined according to the Standard Methods
for the Examination of Water andWastewater. Total phenolic content (TP) was quantified by
Folin–Ciocalteau method. The antioxidant activity was measured by DPPH radical scaveng-
ing activity, reducing power and inhibition of β-carotene bleaching. The identification of the
phenolic compounds and its radiolytic products was carried out by HPLC-DAD-ESI/MS.
To test the hypothesis that the radiolytic effect of γ-radiation could promote the biodegrad-
ability of phenolic acid products, microbial culture growth experiments were performed
using a microbial population of four bacterial strains naturally present in cork wastewater
sedimentation tank samples. Recovery studies of antioxidant compounds present in cork
wastewater were carried out by adsorption/desorption experiments using a synthesized
mesoporous carbon. The toxicity of irradiated cork wastewater and its radiolytic products
was evaluated by the cellular growth inhibition method using different prokaryotic and
eukaryotic cells.
Cork wastewater indicated a low pH of 5.14, a high value of COD (2903 mgO2{`) and a
low biodegradability (BOD5/COD “0.136), that can be explained by the presence of hardly
biodegradable natural compounds. The TSS and TP values are 134 mg{` and 680 mg gallic
acid per litre, respectively. The most abundant phenolic compounds identified were: gallic,
protocatechuic, vanillic and syringic acids, that presented high antioxidant activity. After
irradiation, the results suggested that γ-radiation is a potential technology for wastewater
treatment. The BOD and TSS values are greatly reduced (ě 45%) at 100 kGy. TP and an-
tioxidant activity increase around 33% which opens the possibility of recovery of the added
value compounds to be utilized in other industries. Concerning adsorption/desorption
studies, a 40% recovery of vanillic and syringic acids using activated carbon was achieved.
Non-treated cork wastewater seems to be non-toxic for the majority of the studied cells.
The γ-radiation treatment affected the toxicity of cork compounds for prokaryotic and
eukaryotic cells, which could be related to a cytotoxicity effect of radiolytic products of cork
compounds. Further studies are being carried out to understand these radiolytic mech-
anisms and alternative adsorbents will be tested for selective extraction of the valuable
antioxidants.
IAEA–CN–241–151 Presenter: S. Cabo Verde 333
PA1
PA1-38 Session PA1, Wednesday 14:15 Mihaljević
Detoxification of Aflatoxin B1 and Ochratoxin A by γ-Radiation
B. Mihaljević1, I. Tartaro Bujak1, A. Vulic2, J. Pleadin2, K. Markov3, A.-M. Marjanović4,
and I. Pavicic4
1Ruđer Bošković Institute, Zagreb, Croatia
2Croatian Veterinary Institute, 10000 Zagreb, Croatia
3Faculty of Food Technology and Biotechnology, University of Zagreb, Zagreb, Croatia
4Institute for Medical Research and Occupational Health, Zagreb, Croatia
Corresponding Author: B. Mihaljević, mihozeg@irb.hr
Mycotoxins aflatoxin B1 (AFB1) and ochratoxin A (OTA) are widely distributed food contam-
inants that have adverse effects to animal and human health. In order to reduce mycotoxin
contamination and protect animal and human health, various strategies are applied. Some
studies indicate that γ-irradiation is effective in reducing mycotoxin contamination. There-
fore the aim of this study was to investigate the effect of γ-irradiation on the AFB1 and OTA
degradation as well as toxicity of mycotoxin radiolytic products in vitro.
Mycotoxins stock solutions in methanol (50 mM) were γ-irradiated with doses of 5 and
10 kGy and dose rate of 140 Gy/min using panoramic 60Co source in the Radiation Chem-
istry and Dosimetry Laboratory at the Ruđer Bošković Institute. The dose rate was estab-
lished using the ethanol-chlorobenzene dosimetry system. Molecule structure analysis of
non-irradiated and irradiated AFB1 and OTA was performed by liquid chromatography
tandemmass spectrometry (HPLC-MS/MS). Toxicity of non-irradiated and irradiated AFB1
and OTA (in concentration 1–500 µM; 24 h) was tested on HepG2, SH-SY5Y and Pk15 cells
by quantitative colourimetric MTT assay.
AFB1 and OTA molecules were effectively degraded even at 5 kGy of γ-irradiation. The
signal intensity for non-irradiated AFB1 was 16 times higher than for irradiated AFB1
(5 kGy) and signal intensity for non-irradiated OTA was twice higher than irradiated OTA
(5 kGy). These results indicate that AFB1 has greater susceptibility thanOTA to γ-irradiation.
Besides of fragment ions of AFB1 or OTA with a mass less then the parent ion, several
radiolytic products with mass higher then the parent ion were detected. These results
strongly indicate the contribution of addition reactions caused by free radicals generated
in solution during γ-radiolysis. Results on cytotoxicity indicate that radiolytic product
of irradiated AFB1 and OTA are less toxic to HepG2, SH-SY5Y and Pk15 cell lines than
non-irradiated mycotoxins (parent compounds).
Based on the AFB1 and OTA structure modifications induced by γ-irradiation, free radical
mechanisms are operative in the irradiation of mycotoxins. Additionally, cell viability assay
demonstrated that mycotoxins radiolytic products are less toxic to cells than parent non-
irradiated compound. Based on these results γ-irradiation can be considered as an effective
method for the detoxification of mycotoxins.
334 IAEA–CN–241–156
PA1
Mimount Session PA1, Wednesday 14:15 PA1-39
Dosimetric Evaluation in Industrial Gammagraphy Operations
S. Mimount1, O. K. Hakam2, K. Sahaimi3, K. Talsmat1, and R. Alami1
1Centre National de l’Energie des Sciences et des Techniques Nucléaires (CNESTEN), Rabat, Morocco
2Ibn Tofail University, Kenitra, Morocco
3Qualite Controle Mesure (QCM) Sarl, Kenitra, Morocco
Corresponding Author: S. Mimount, samira.mimount@gmail.com
In this work, we developed a dosimetry study in industry in order to examine the parameters
influencing the operators dosimetry in Gammagraphy interventions. These parameters
are determined in a description of the practice and are subject to individual measures in
real working conditions, using TLD dosimeters for estimation of the whole body dose
[Hpp10q] and the extremities and bone surface dose [Hpp0.07q]. This approach established a
dosimetric estimate including various phases of radiographic testing under real conditions
of the intervention, but also during the phases of transport and handling γ-radiography, in
order to prevent and reduce the risk of exposure to these operators.
IAEA–CN–241–255 335
PA1
PA1-40 Session PA1, Wednesday 14:15 Mohamed Moustafa
Application of Isotopic Techniques Using Mathematical Models
in Environmental Process
W. Mohamed Moustafa1
1National Center for Radiation Research and Technology (NCRRT), Nasr City, Cairo, Egypt
Corresponding Author: W. Mohamed Moustafa, wafaasalem21@yahoo.com
During the last few decades, the use of tracer techniques in dealing with a variety of
hydrological and hydrogeological problems have proved their value in improving the
assessment and development of water resources. In this regard, the methodologies based
on observations of temporal and spatial variations of naturally occurring isotopes, often
referred to as “environmental isotope techniques”, are widely employed as an integral part
of the routine investigations related to various hydrological systems, and particularly in
regional groundwater aquifers.
A substantial amount of isotope data was so far collected and published from hydrological
applications of natural isotopes, however, it is often used for qualitative inferences to be
made of the system under study, and improve understanding of processes and dynamics of
water circulation. The need for improved methodologies for quantitative evaluations to be
made from isotope datawith regards the relevant physical parameters of the system has been
recognized. This has been the main motivation to improve the progress on mathematical
models for quantitative evolution of isotope data in hydrology.
Isotope-hydrology (stable and radio isotopes) has been previously used to investigate water
resources, interconnection between different aquifers, relationships between surface and
groundwater as well as direction of recharge, etc. Currently, mathematical modelling using
isotopes is used in modern ecosystem studies to investigate the source, direction, quantity
and transport of pollutant, moisture isotope fluxes in present and past climate systems, as
well as transit time estimation in catchments hydrology.
Focusing our discussion on the use of environmental tracers in water molecule itself such
as, 18O, 2H, and 3H. These ideal tracers are applied by precipitation and are generally
distinct isotopically, which makes them reliable tracers of subsurface flow and groundwater
recharge mechanism. Two case studies were chosen, the first case illustrates the calculation
of the mean residence time for groundwater in the investigated area, using tritium. The
age of groundwater was found in the range from few tens to several hundreds of years,
reflecting the recharge mechanism and possibility of contamination. The second case study
was applied using deuterium isotope balance approach to separate evaporation and seepage
rates per year in lake area.
336 IAEA–CN–241–083
PA1
Morgunov Session PA1, Wednesday 14:15 PA1-41
The Numerical Simulation of Cultural Heritage Radiation
Treatment by Monte Carlo Method
V. Morgunov1
1Ukrainian Engineering and Pedagogical Academy, Kharkiv, Ukraine
Corresponding Author: V. Morgunov, volodymyr.morgunov@gmail.com
Radiation processing techniques are in wide use in for disinfection and consolidation of
archived materials and cultural heritage artefacts. The maximum dose (Dmax), which can
be absorbed by product without changing its properties, is known from research phase. So,
minimal absorbed dose (Dmin) should be transferred to the product to achieve disinfection
and this dose shouldn’t be more than maximum dose. The location and magnitude of the
dose minimum and maximum is critical to process control, optimized irradiation configu-
rations as it affects both disinfection and product properties. Reliable product dose-maps
are necessary for identification of these critical process parameters and may involve time
consuming and laborious dosimetry. In some cases determination of the dose-maps is
difficult to produce by experiment. Such cases are very often occur during cultural heritage
artefacts radiation treatment. In such situations numerical simulation can be used. After
consideration of all possible software toolkits for passage of ionization radiation through
the matter, GEANT4 was chosen. The CADMesh library was implemented in developed
code to input complicated geometry. The radiation sources (plaque and cylindrical) were
input into the code. Their activities, loading date into operation can be loaded from .csv
file. The comparison between measurements and simulated results were made, with the
simulated results showing good agreement with measured data.
IAEA–CN–241–072 337
PA1
PA1-42 Session PA1, Wednesday 14:15 Mouhib
Upgrading of 60Co in Temporary Pool for Dry Storage
Irradiation Facility SIBO INRA/Tangier Morocco
M. Mouhib1, M. Chentouf1, and A. Guessous2
1Institut National de la Recherche Agronomique (INRA), Tanger, Morocco
2University of Ibn Tofail, Kenitra, Morocco
Corresponding Author: M. Mouhib, momouhib@yahoo.fr
In any irradiation facility, upgrading of 60Co activity is one of the most important main-
tenance operations, which should be done periodically to maintain the dose rate in the
irradiation process given the decay of 60Co. In general there are two kinds of irradiator with
either wet storage or dry storage of 60Co in the facility. For wet storage facilities, the 60Co
upgrade receives the cobalt in a supplier provided shipping container and the source is
transferred into the pool of the facility to the source rake of the irradiators. For dry storage,
cobalt upgrade is done at the supplier facility by shipping the entire cobalt irradiation
container, which serves also as transport container, back to the supplier to upgrade the
source 60Co.
The Station d’ionisation de Boukhalef (SIBO), is a panoramic irradiator with dry storage of
60Co in a container which is also used as the transport container in the first loading. We
have been faced with a problem of the container transport and we need to find a solution
to upgrade the 60Co. Our proposed solution is to bring cobalt in a supplier container and
transferring the new sources to our facility container using a temporary pool fabricated in
the facility.
The objective of this paper is to show a case study experience. This operation has been
considered as a success story by the IAEA and opened this solution method for similar
irradiators in other countries which have the same problem. Its execution was a real
application of the nuclear security system installed in the facility and during the transport
of 60Co.
338 IAEA–CN–241–225
PA1
Mouhib Session PA1, Wednesday 14:15 PA1-43
Enhancing Safety and Control Features of Radiation Processing
Facility SIBO INRA/Tangier Morocco
M. Mouhib1
1Institut National de la Recherche Agronomique (INRA), Tanger, Morocco
Corresponding Author: M. Mouhib, momouhib@yahoo.fr
The automatic control system is one of the central parts of all irradiation facilities. The
level of this control is always implemented to achieve strict safety procedures in routine
facility use. However, sometimes the system is limited to the minimum legal regulation
required due to economical restrictions; some commercial systems are generally made by
manufactures of industrial facility and considered in the price of the irradiator. In some
cases there is some specific irradiation facility with specific control system. For this kind of
irradiator the control system can be developed and upgraded according to feedback from
operating experiences and in accordance with industrial experiences. These upgrading
procedures are also used as input by others to upgrade their systems.
The objective of this paper is to share a local experience in upgrading the safety systems
and special upgrading of 60Co for the irradiator. This work has been done with other
works related to security and 60Co upgrading which are published in other scientific paper
and concerns 1) Upgrading of 60Co in SIBO irradiator in Tangier (an operation made in
collaboration with the IAEA and has been a success story of the year 2014 during the
general conference of IAEA), and 2) Installation and upgrading of the security system
in accordance with the Global Threat Reduction Programme to reduce the threat of a
Radiological Dispersion Device (RDD) in collaboration with The United States Department
of Energy’s National Nuclear Security Administration (NNSA).
IAEA–CN–241–226 339
PA1
PA1-44 Session PA1, Wednesday 14:15 Ounalli Mejri
The Efficiency of Radiation Processing by the Tunisian 60Co
Industrial Irradiator after 16 Years of Use
L. Ounalli Mejri1, N. Mejri1, A. Mejri1, N. BenMiloud1, and J. Chatti1
1National Center for Nuclear Sciences and Technologies (CNSTN), Sidi Thabet, Tunisia
Corresponding Author: L. Ounalli Mejri, leila.ounalli@cnstn.rnrt.tn
Since its commissioning at 1999, the Tunisian 60Co irradiator has been mainly used for
sterilization of single use medical devices and decontamination of agro-food products. Now
at its third half-life, the irradiator has a low source activity. This activity leads to a very
low dose rate and requires a very long processing time. Therefore, it becomes judicious to
study the absorbed dose distribution in the processed product. In this study, evaluation of
the irradiator performance was carried out by placing multiple Fricke dosimeters. Dose
mapping in the front and back planes of the irradiated product has been carried out and
microbiological analysis has been established.
Taking into account its huge virtue in different diseases (cancer, heart-vascular, Cholesterol-
lowering effect, etc.) and the short time required for their irradiation, garlic Allium sativum
L was considered in this study. Boxes containing garlic, with dimension of 24 ˆ 20.6 ˆ
15.5 cm3, were irradiated with 50, 100 and 150 Gy during 7, 18 and 29 min, respectively.
The determination of radiation doses measured by Fricke dosimeters are performed using
UV-visible spectrophotometer. Thus, yeast, mold and mesophilic bacteria were quantified
at different doses.
The cartography performed using Fricke dosimeters allowed the determination of the dose
uniformity ratio (Dmax{Dmin). Two-sided (front and back) irradiation resulted in a dose
uniformity ratio of about 1.5 for garlic and 1.13 for rock wood (used for cartography). For
the front and back planes, the results showed a symmetrical distribution relatively to the
horizontal XY plane. The maps showed that the absorbed dose reached the maximum in the
centre and decreased slightly keeping the same order of magnitude. Statistical uncertainty
of Fricke dosimeters is about 2% and systematic error related to the source activity is below
10%.
Results obtained for the microbiological analysis of the irradiated and nonirradiated garlic
showed that irradiated garlic with known absorbed doses harboured bacteria. The high dose
irradiated samples (150 Gy) were free of viable bacteria. According to the FAO permissible
limits, irradiated garlic never exceeded these permissible counts. Considerable number of
yeast and mold (20000 cfu/g) were detected only in nonirradiated samples. After 50 Gy
irradiation dose, the number of these microorganisms decreased to (61 cfu/g) and continue
to be absent for all other doses. The number of total aerobic mesophilic bacteria decreased
by the irradiation. This is in agreement with literature for different food commodities.
Performed studies showed that the irradiation facility at third half life gave an uniform
absorbed dose rate distribution, but, the processing efficiency of the actual source to preserve
fresh food (fruits, vegetables, salads and meat products) in terms of microbiological safety
is not reliable regarding the very low absorbed dose rate and the required long irradiation
time. However, preserving food with low irradiation time requirements (garlic, onion, . . . )
is possible at the current activity while waiting for the 60Co source pencil reloading.
340 IAEA–CN–241–300
PA1
Pant Session PA1, Wednesday 14:15 PA1-45
Measurement of Voidage/Holdup in Industrial Process Systems
Using γ-Ray Densitometry
H. J. Pant1, V. K. Sharma1, and J. S. Samantray1
1Bhabha Atomic Research Centre (BARC), Mumbai, India
Corresponding Author: H. J. Pant, hjpant02@gmail.com
Multiphase flow reactors are commonly used in industry. One of the requirements for
the efficient operation of these reactors is to have intimate contact or mixing between the
different phases. Any spatial nonuniformity of the phases will adversely affect the process
efficiency. Therefore, it is important to characterize the void fraction and holdup, and their
spatial distribution inmultiphase flow reactors. The γ-ray transmission technique commonly
known as γ-ray densitometry is one of the commonly used techniques for measurement of
voidage or phases holdup in multiphase flow systems because of its noninvasive nature
and applicability to opaque systems. In γ-ray densitometry, a collimated radiation source
(usually 137Cs) and a scintillation detector are mounted in a horizontal plane across the
diameter of the flow system under investigation. The narrow mono-energetic beam of the
γ-rays with an incident intensity passes through the system (walls and material within the
system). A fraction of the incident beam is attenuated within the system and the transmitted
intensity of the γ-rays is recorded by the detector connected to a radiation counting system.
Let us consider an industrial process system, i.e., gas-solid fluidized bed system and record
intensity of transmitted γ-rays at three different conditions of operation, i.e., with empty
system (with air), with solids and with two phase flow (fluidized condition), then the line
averaged void fraction of the fluidized bed is estimated using equations detailed in r1s:
The technique was used for estimating voidage/holdup in pilot-scale two phase flow sys-
tems, i.e., fluidized beds and bubble column reactor to evaluate mixing of the two phases
r1, 2s. The results of the studies helped to understand the flow dynamics of the phases and
validate or improve the design of the system.
References
r1s S. Bhowmick, et al., Ind. Eng. Chem. Res., 54, #46, 11653–11660, (2015).
r2s D. Mandal, et al., Powder Technology, 226, 91–98 (2012).
IAEA–CN–241–449 341
PA1
PA1-46 Session PA1, Wednesday 14:15 Prieto Miranda
Dosimetric Characterization of the ISOGAMMA LLoCo
Irradiator
E. F. Prieto Miranda1, A. Chavez Ardanza1, D. L. Moreno Alvarez1, and
G. Barrera Gonzalez1
1Centro de Aplicaciones Tecnológicas y Desarrollo Nuclear (CEADEN), Havana, Cuba
Corresponding Author: E. F. Prieto Miranda, efprieto@ceaden.edu.cu
All irradiation facilities must, before being put into operation, perform dosimetric charac-
terization of the radiation field. This data obtained from the commissioning dosimetry is
used to determine the irradiation times necessary so that irradiated products receive the
required absorbed dose value, and establishes the facilities operational parameters, such as
dose uniformity ratio, and maximum and minimum dose positions.
The ISOGAMMA LLCo radiation facility at CEADEN had no such procedure carried out
during commissioning by the manufacturer. Thus, it was necessary to perform dosimetric
trials to characterize the dose distribution in the irradiation chamber of the facility, to
contribute to the correct operation of the facility, and ensure the quality of future radiation
process.
The experimental measurement points were selected taking into account the geometry of
the irradiation chamber and dosimeters were distributed in the areas where the maximum
and minimum dose values were expected. Initially, the Fricke dosimetric system was used
to determine dosimetric characterization, and considering the cylindrical geometry of the
irradiation chamber and its dimensions, the chamber was divided into three study zones.
The dosimeters were measured by using the spectrophotometric method. Later, the alanine-
ESR dosimetric system was employed to determine the dose distribution and the chamber
was divided into six study levels, and alanine dosimeters were measured by using the
electron spin resonance (ESR) technique with MiniScope 400 equipment.
In this experimental work, the dosimetric characterization of the ISOGAMMA LLCo ra-
diation facility was measured with two different dosimetric systems. The measured dose
distribution has a similar profile for both dosimetric systems and the highest dose values
are observed in the central part of the radiation chamber and the lower dose values in the
upper and bottom parts.
342 IAEA–CN–241–114
PA1
Pucić Session PA1, Wednesday 14:15 PA1-47
γ-Irradiation in Protection of Cultural Heritage: Effects on
Model Cellulose Based Textiles
I. Pucić1, K. Marušić1, K. Kavkler2, and B. Mihaljević1
1Ruđer Bošković Institute, Zagreb, Croatia
2Institute for the Protection of Cultural Heritage, Restoration Centre, Ljubljana, Slovenia
Corresponding Author: I. Pucić, pucic@irb.hr
Cellulose-based textiles are very common materials in cultural heritage (CH) collections
(garments, upholstery, etc.) and in art (painting canvases). Natural textile fibres are suscep-
tible to biologic damage, particularly by insects and fungi which is a serious problem in the
preservation of such CH objects. Art canvases as well are commonly coated with animal
glue what makes them more susceptible to fungal attack.
Ionizing radiation has been recognized as a fast and efficient treatment against attacks by
living organisms, particularly insects. At theRadiationChemistry andDosimetry Laboratory
of the Ruđer Bošković Institute, radiation treatment of CH items has been ongoing for about
25 years. Along numerous wooden, paper and leather objects, textile artefacts (mostly
of ethnological significance) were efficiently disinsected by irradiation to 2 kGy or less.
However, the application of higher doses needed for the control of fungi has to be justified,
particularly considering the effects on aged and deteriorated materials. Because of that, this
study is aimed at assessing whether there are irradiation side-effects on cellulose-based
textile fibres and to identify the type and the extent of damage type if present. The role of
glue-coating on radiation sensitivity of model canvases is also investigated.
The study consists of two parts. The first part was intended to identify the effect of irradiation
and ageing. A set of cotton and linen model textile samples were irradiated and a part was
also artificially aged. Two γ-irradiation doses were selected: 6 kGy that is often used in
treatment of fungi and amuch higher dose of 120 kGy that is not used in radiation treatment
but is expected to cause detectable side-effects. The samples were irradiated in contact with
air at the dose rate of 2.8 Gy/s. In a second part of the study, linen samples as a model
for painted canvas were coated with animal glue prior to irradiation. Those samples were
exposed to a range of doses between 2 and 50 kGy at dose rates 0.1 and 9.8 Gy/s, also in
contact with air. Before the postirradiation analysis, the glue was removed. The samples
were studied by FTIR-spectroscopy, microscopy and thermal techniques.
Slight changes due to irradiation of model cotton and linen textiles were observed only at
the higher dose of 120 kGy but were comparable or lesser that those brought in by ageing.
Although the process of glue removal from the model canvas samples might have somewhat
obscured the results, it seems that the coating reduces radiation sensitivity of model canvas.
Since doses up to 10 kGy are needed for control of the most common fungi on CH textile
materials the results are encouraging. Efficient radiation treatment of fungal contamination
should case no undesirable changes and thus be acceptable to conservator specialists.
IAEA–CN–241–239 343
PA1
PA1-48 Session PA1, Wednesday 14:15 Razem
Dosimetric Calibration of a Panoramic 60Co γ-Ray Source
D. Razem1, Z. Knezevic1, M. Majer1, B. Mihaljević1, and S Miljanić1
1Ruđer Bošković Institute, Zagreb, Croatia
Corresponding Author: D. Razem, razem@irb.hr
The panoramic 60Co source at the Ruđer Bošković Institute is the only irradiation facility in
Croatia suitable for a variety of applications: frommedium range doses used in radiobiology
and accident dosimetry to high doses pertaining to radiation processing and research in
radiation chemistry. In November 2015, thanks to IAEA support, the source was upgraded
with an additional 3.5 PBq. The results of precise dosimetric calibration and determination
of dose distribution curves typical of the cylindrical γ-ray panoramic source geometry are
presented.
Because of the cylindrical shape of the source, the radiation field also has a cylindrical
symmetry and is best described by cylindrical coordinates. Radiation field mapping was
performed with the ethanol-chlorobenzene (ECB) dosimetry system which was developed
50 years ago in our Radiation Chemistry and Dosimetry Laboratory and subsequently
accepted as an international standard (ISO/ASTM 51538). The commercial 5 cm3 pharma-
ceutical ampoules were used for irradiations. Irradiated ECB dosimeters were analyzed
for chloride ion concentration by two methods: oscillometry before opening; after open-
ing aliquots were taken for mercurimetric titration. Oscillometry was performed by an
oscillotitrator Model OK-302/1 (Radelkis Electrochemical Instruments, Budapest). After
measurements, the doses were evaluated from the previously determined calibration curves.
For mercurimetric titration, the standardization of Hg`2 solution used for titration with
standard NaCl solutions was performed daily before the analysis of irradiated dosimetric
solutions. All doses were expressed as “absorbed dose to water”. For dosimetry calibration
and “transit” dose measurements an ionization chamber type 2581 and a Farmer Dosimeter
type 2570 (NE Technology Limited, England) were used.
Dose mapping in horizontal and vertical planes was performed with ECB dosimetry system,
as follows: a) A check of the radiation field angular symmetry was performed inside the
annular space enclosed by the source rack; b) The dependence of the dose rateD on radius r
from the axis of the cylinder was measured at two heights: at h “ 0 cm (the horizontal plane
passing through the centre of the source cylinder) and at h “ 100 cm; c) The dependence of
dose rate D on height h was measured at two radii: r “ 50 cm and r “ 100 cm from the
source axis, both in vertical planes through the axis. The “transit dose” was measured at
different radii at h “ 0.
It was shown that the radiation field of the cylindrical γ-ray panoramic source is fully
describable by using only two parameters, radius r from the axis and distance h from the
reference horizontal plane.
The support of the IAEA in ensuring timely supplies of radioactive 60Co over the years,
especially through the recent Technical Co-operation Project CRO/1/006 (2014-2015) is
gratefully acknowledged.
344 Presenter: B. Mihaljević IAEA–CN–241–154
PA1
Rushdi Session PA1, Wednesday 14:15 PA1-49
EPR Dosimetric Potential of Ammonium Oxalate Monohydrate
in Radiation Technology
M. Rushdi1, B. Wafaa2
1Sudan Atomic Energy Commission, Khartoum, Sudan
2Egyptian Atomic Energy Authority (EAEA), Cairo, Egypt
Corresponding Author: M. Rushdi, mohdrushdi000@gmail.com
This study aims to examine the dosimetric properties of the ammoniumoxalatemonohydrate
(COONH4)2H2O under low and high radiation doses. The EPR spectra of ammonium
oxalate have the spectroscopic splitting g-factors of 2.0095 and 2.0047. Results indicate that
the dose-response curves have a good linearity in the range between 10–1000 Gy for low
doses. Slight sub-linearity has been found in high dose region up to 25 kGy. The effects
of temperature and humidity on the EPR signal amplitude of the irradiated samples are
studied. Stability of the irradiation rods upon storage (signal fading) was also investigated.
Energy dependence has been found within 38% at the range below 100 keV. Slightly energy
dependence within 4% over the energy range 6–10 MeV has been recorded. The overall
uncertainty of this dosimetry system is 4.64% (2σ) in low dose range and 3.67% for the high
dose range.
IAEA–CN–241–314 345
PA1
PA1-50 Session PA1, Wednesday 14:15 Salgado
Development of a Digital Model for the Dosimetry of the 60Co
Irradiator at the National Polytechnic School of Ecuador
F. Salgado1
1Escuela Politécnica Nacional (EPN), Quito, Ecuador
Corresponding Author: F. Salgado, fsalgadot@hotmail.com
This project presents the development of a digital model using the MCNP programme to
simulate the dosimetric distribution of the 60Co irradiation facility of the National Polytech-
nic School of Quito, Ecuador, with a 100 kCi installed capacity. First, a map of absorbed
dose was obtained with Fricke dosimeters distributed through the irradiation chamber,
at five different distances fixed from the source (20, 40, 60, 100, 165 cm). An irradiation
time based on the time required for a dose of 300 Gy at 20 cm from the source was set to
measure the dose. This time was fixed for all the distances. The irradiation process was
performed three times. To define the input data for the model it was necessary to establish
the geometry, dimensions, materials and chemical compositions forming the irradiation
chamber. To calculate the absorbed dose, a quantizer data or “tally” was used to determine
the energy deposited in a given area, called cell. In order to characterize the twelve pencils
composed the 60Co source, the SDEF code was applied to simulate a fixed source and
photons. Several changes at the starting model input data were needed to set and improve
the performance. The final digital model was achieved with an error of less than 15% when
compared with data obtained by Fricke dosimetry, therefore this model was validated.
346 IAEA–CN–241–363
PA1
Šegvić Klarić Session PA1, Wednesday 14:15 PA1-51
γ-Irradiation for Cultural Heritage: Treatment of Selected Fungi
on Linen Textile
M. Šegvić Klarić1, I. Pucić2, A. Božičević3, K. Marušić2, and B. Mihaljević2
1Faculty of Pharmacy and Biochemsitry, University of Zagreb, Zagreb, Croatia
2Radiation Chemistry and Dosimetry Laboratory (RCDL), Ruđer Bošković Institute, Zagreb, Croatia
3Academy of Fine Arts, University of Zagreb, Zagreb, Croatia
Corresponding Author: M. Šegvić Klarić, msegvic@pharma.hr
A common carrier for paintings is glue-coated linen that is vulnerable to fungal biodeteri-
oration. The study aimed to assess antifungal effect of γ-irradiation doses and dose rates
against naturally occurring mycobiota and artificially inoculated fungal colonizers common
for cellulose materials like linen. The composition of natural mycobiota on glue-coated linen
(initial level) and eventual postirradiation recovery of mycobiota were analyzed.
The initial level of common fungal colony-forming mycobiota on model glue-coated linen
textile was determined by plate count method upon 7 days of incubation (at 25˝C and 70–
80% r.h.) and the data expressed as the number of colony-forming units per gramme (cfu/g).
Next, linen samples were separately inoculated with selected primary (Aspergillus jensenii),
secondary (Cladosporium spaherospermum) and tertiary colonizers (Trichoderma harzianum) at
concentration of 10 000 cfu/g. Inoculated linen and controls were incubated as described.
One group of samples was analyzed immediately upon the incubation while the rest of the
samples were irradiated via 60Co source at RCDL to doses of 2, 7, 20 and 50 kGy, at dose
rates of 0.1 and 9.8 Gy/s and analyzed after incubation for 0, 7, 14 and 28 days.
Alternaria spp., Aspergillus spp., Cladosporium spp., Fusarium spp., Penicillium spp. and yeasts
comprised naturally occurring mycobiota, in initial concentrations of 1000 cfu/g (moulds)
and 10 000 cfu/g (yeasts). These fungi were non-homogeneously dispersed on glue-coated
linen. On incubation in humid atmosphere the concentration of mycobiota increased for four
orders of magnitude. Similar increase was obtained for non-irradiated artificially inoculated
samples. All applied doses and dose rates were effective against primary and tertiary
colonizers but not for secondary colonizers and linen mycobiota. Doses of 2 and 7 kGy was
ineffective in reduction of linenmycobiota to the initial level; after 28days of incubation fungi
were recovered up to 1 000 000 and 100 000 cfu/g, respectively. Dose of 20 kGy (0.1 Gy/s)
reduced Cladosporium spp., and Alternaria spp. to 10000 cfu/g; Penicillium spp.was reduced to
the initial level while yeasts, Aspergillus spp., and Fusarium spp. recovered in concentrations
below initial. For both 7 and 20 kGy dose rate of 9.8 Gy/s was more effective in fungal
elimination than 0.1 Gy/s, while for 2 kGy the dose rate effect was inconsistent. Upon
exposure to 50 kGy sterile white mycelia was recovered on few plates C. sphaerospermum
survived radiation with 2, 7 and 20 kGy, showing the similar recovery pattern as obtained
for Cladosporium spp. After treatment with 7 and 20 kGy (0.1 Gy/s) cladosporia recovered
between 7th (or 14th) and 28th day in concentrations between 1000 and 1 000 000 cfu/g.
The same doses applied at 9.8 Gy/s inhibited recovery of C. sphaerospermum.
For successful γ-radiation reduction of fungal contamination on cultural heritage it is
essential to determine mycobiota composition and to irradiate at an appropriate dose rate.
IAEA–CN–241–187 347
PA1
PA1-52 Session PA1, Wednesday 14:15 Shah
Personal Radiation Dosimetry at Radiological Facilities, Nepal
B. R. Shah1, B. Rijal1, and P. Acharya1
1Faculty of Science, Nepal Academy of Science and Technology (NAST), Lalitpur, Nepal
Corresponding Author: B. R. Shah, buddharshah25@gmail.com
The saga of using ionizing radiation is long back in Nepal especially in medical sector. With
the introduction of radiation therapy and nuclear medicine, it has been felt the need of
monitoring occupational radiation exposure. Only few hospitals three to four are monitor-
ing their staff by sending thermoluminescent dosimeter (TLD) badges to Bhabha Atomic
Research Centre, Mumbai, India. Over 95% radiation workers are never been monitored for
their radiation dose. However, it is a mandatory by ILO that every radiation worker should
be monitored for radiation exposure. To meet this requirement from the overwhelming
requests from various hospitals, the Nepal Academy of Science and Technology (NAST)
initiated this work in 2013 with the assistance provided by the IAEA.
The government of Nepal has assigned NAST to provide the dosimetry service for radiation
workers in Nepal. For this service, a dosimetry setup comprising a Harshaw 6600 Plus
TLD Reader along with TLD cards (TLD 100 LiF:Ti.Mg) has been installed in December
2015 at the Physical Science Laboratory, NAST. The complete dosimetry system became
operational in March 2016 with the help of IAEA expert mission. Under a test service,
Manamohan Memorial Cardiovascular and Transplant Centre (MMCTC) was chosen where
22 TLD cards were earlier provided to the personnel to wear and the cards were read out for
dose assessment. The first personal dosimetry report for one month was issued in March
2016 for this hospital. The penetrating dose Hp(10) and skin dose Hp(0.07) of individuals
have been reported. The absorbed dose distribution of personnel show that few radiation
workers received significant radiation in that duration.
348 IAEA–CN–241–387
PA1
Son Session PA1, Wednesday 14:15 PA1-53
Electron Beam Techniques for Air Pollution Control
Y.-S. Son1, T.-H. Kim1, and S. Yu1
1Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
Corresponding Author: Y.-S. Son, sonys@kaeri.re.kr
Various technologies such as absorption, adsorption, incineration, biofiltration and advanced
oxidation have been developed to treat air pollutants. However, these methods have some
limitations such as a high pressure drop, short lifespan, large site, economics and formation
of secondary pollutants. To solve these problems, recently, advanced oxidation processes
have been studied. An electron beam (EB) technology is one of themost promising advanced
technologies due to its special characteristics. The EB technologies for volatile organic and
odorous compounds treatment are introduced in this paper. The removal efficiency of these
compounds by an EB processing is discussed in diverse conditions, such as different initial
concentrations, background gases, absorbed doses, relative humidities, etc. Furthermore,
the characteristics and effects on newEBhybrid technologies designed to overcome problems
of only EB system are reviewed. In additional, the limitations and potentials of EB technology
for air pollution treatment are also discussed.
The author would like to thank Clarian H. for her insightful contributions. This research
was supported by the Nuclear R&D programme through the National Research Foundation
of Korea (NRF) funded by the Ministry of Science, ICT and Future Planning.
IAEA–CN–241–084 Presenter: S. Yu 349
PA1
PA1-54 Session PA1, Wednesday 14:15 Souza
Dosimetric Properties of MgB4O7:Ce and MgB4O7:Ce, Li for
Thermoluminescence Dosimetry Applications
D. Souza1, L. Souza1, P. L. Antonio2, and L. V. E. Caldas2
1Universidade Federal de Sergipe, São Cristóvão, Brazil
2Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), São Paulo, Brazil
Corresponding Author: D. Souza, divanizia@gmail.com
Thermoluminescent dosimetry is known as a well-established technique for monitoring
radiation dose in medical practices. Some most used thermoluminescent dosimeters (TLDs)
are: LiF:Mg,Ti (TLD-100), CaF:Mn, CaSO4:Dy, Li2B4O7, and aluminophosphate glasses.
Recent studies have demonstrated that borates can be very useful for TL dosimetry because
their compounds may be more sensitive to radiation than the commercial dosimeters as
TLD-100. Furthermore, compounds with 10B allow the detection of thermal neutrons
(E ă 0.25 eV). They also have other good dosimetric properties, such as linear dose response
over a large absorbed dose range, effective atomic number close to that of human tissue,
and a simple TL emission curve with a single peak. However, there is not much discussion
about preparation routes for dosimeters based on borates and on the structure of their
compounds. Among these, we examined thermoluminescence properties of magnesium
tetraborate doped with cerium (MgB4O7:Ce) and co-doped with lithium (MgB4O7:Ce,Li).
Some important TL properties were investigated such as: dose response for γ and β, fading
and kinetic parameters of TL curves. To study TL response, the material was investigated in
pellet format (3 mm diameter) that were irradiated with sources of β particles (90Sr/90Y)
and γ-rays (60Co) with different absorbed doses. The TL responses were measured using
an TL/OSL reader (TL/OSL reader Riso). The results showed that the materials have great
potential for TLD dosimetry, presenting low fading of TL signal (ă 3% in one month) and
prevalence of first-order TL peak. The dose response curves also show that saturation occurs
at higher doses (up to 1000 Gy) and the kinetic parameter shows TL curve follow kinetic of
first order.
350 IAEA–CN–241–222
PA1
Tegze Session PA1, Wednesday 14:15 PA1-55
Radiolysis Induced Degradation of Fluoroquinolones
A. Tegze1, E. Takács2, and E. Illés2
1Óbuda University, Budapest, Hungary
2Hungarian Academy of Sciences, Centre for Energy Research, Budapest, Hungary
Corresponding Author: A. Tegze, tegzeanna01@gmail.com
The fluoroquinolones are synthetic antibiotics and inhibit very effectively gram-negative
bacteria, but do not totally degrade during common wastewater treatments, hence, they will
be released in the environment. The environmental exposure of the fluoroquinolones can
lead to bacterial resistance. Because these compounds do not degrade during the common
wastewater treatments radiolysis as an advanced oxidation process was investigated.
Gamma-radiation induced degradation of two frequently used fluoroquinolone antibiotics,
ciprofloxacin and norfloxacin was investigated with UV-Vis spectrophotometry, with HPLC-
UV and with organic sum parameter measurements (chemical oxygen demand (COD)
and total organic carbon (TOC)). The samples were irradiated with doses between 0.2 and
10 kGy. The HPLC analysis was performed on a C18 column, with gradient elution and
with diode array detection. In the case of UV-Vis spectrophotometry the solutions were
saturated with nitrogen, air or dinitrogen-oxide before the γ-radiation. In some cases tert-
butanol was applied to scavenge the hydroxyl radicals. At the measurements of organic
sum parameters and the HPLC analysis, the fluoroquinolone solutions were saturated
with air. The degradations of ciprofloxacin and norfloxacin were also investigated with
pulse radiolysis technique. Microsecond pulse radiolysis experiments were performed with
4 MeV accelerated electrons, with electron pulse length of 800 ns. The detection was kinetic
spectrophotometric. An optical filter was used because of the bleaching below 400 nm in
the case of fluoroquinolones. Transient absorption spectra of the intermediates produced
by reactions with hydrated electrons were calculated.
The hydroxyl radical-induced degradation was the most efficient comparing to the other
reactive radicals like hydrated electron and hydrogen atom formed during water radiolysis.
The reaction with hydrated electrons was also effective, in this case yellow degradation prod-
ucts were formed. Based on the literature these products were presumably isatin analogues.
The COD values decrease approximately linearly with the dose. The decrease was faster for
low doses, presumably because the more easily degradable compounds degrade first. The
TOC values decreased also approximately linearly with the dose and the results in case of
ciprofloxacin and norfloxacin were very similar. HPLC analysis with diode array detection
showed that three intermediates were produced by γ-radiolysis. The parent compound
and one of the intermediates were totally degraded, and two other intermediates were
partially degraded with the increasing dose. The concentration of the parent compound
decreased strongly with the absorbed dose. Pulse radiolysis experiments showed that hy-
droxyl radical reacts with the parent compound and one radical intermediate was produced
during 5 µs, and then it degraded. In the case of hydrated electrons, presumably two radical
intermediates were produced, and then it degraded in microsecond timescale.
The experiments showed that the degradation and mineralization of fluoroquinolones
linearly depends on the absorbed dose. The removal of fluoroquinolones from water was
effective in the case of γ-radiolysis and also in the case of pulse radiolysis.
IAEA–CN–241–236 351
PA1
PA1-56 Session PA1, Wednesday 14:15 Trabelsi
Tunisian Experience Assessment of Installing a Pilot 60Co
Source for Irradiation
M. H. Trabelsi1, M. Kraiem1, and Z. Trabelsi1
1National Center for Nuclear Sciences and Technologies (CNSTN), Sidi Thabet, Tunisia
Corresponding Author: M. H. Trabelsi, mohamed.trabelsi@cnstn.rnrt.tn
Radiation processing technology started in Tunisia by the installation of a pilot plant γ-
irradiator in 1999 in National Centre for Nuclear Science and Technology (CNSTN) situated
at about 20 km north of the capital Tunis. This facility was established with the support of
the IAEA in the frame of the technical co-operation assistance programme and the French
Atomic Energy Commission (CEA).
The facility is equipped with 60Co source with dry storage and an initial activity of 100 kCi
in 1999 (10 kCi in 2016). The source consists of telescopic 60Co source (08 of C188 pencils-
from Nordion), this french design was logged in a concrete shielding room about 1.7 m of
thickness.
This irradiation facilities are designed to be used for the promotional activities of radiation
processing applications, in particular for conservation of foodstuff, sterilization of medical
devices conservation of art objects and also dedicated to play a great role in enhancing
research and development work and providing services to industries mainly in the fields
mentioned above and to gives more competitiveness for products dedicated for export to
European Union countries.
In this reason Tunisia has implemented a regulation that authorizes radiation sterilization
of various pharmaceuticals and foodstuffs. The poster will focus on the activity of radiation
technology by Tunisian pilot plant, and show the socio-economic advantages in industry
and scientific research during fifteen years of this technology in the country, and discuss
the goals achieved.
352 IAEA–CN–241–248
PA1
Tripathi Session PA1, Wednesday 14:15 PA1-57
γ-Radiation-Co-Cryogelation Induced Synthesis of Macroporous
rpCryogels for Bioengineering Applications
A. Tripathi1, J. S. Melo1
1Bhabha Atomic Research Centre (BARC), Mumbai, India
Corresponding Author: A. Tripathi, anujtri@barc.gov.in
Polymeric porous scaffolds are a key component in several bioengineering and biomedical
applications. In a recent development, we have introduced a novel approach for the design-
ing of macroporous matrices by combining γ-radiation with cryogelation technology. This
new prototype has been optimized and compared with the classical cryogelation technology.
The acrylic derivatives like acrylamide (AAm) and N-(2-hydroxyethyl) methacrylamide
(HEMA) have been used in our study as the model precursor units considering their inert
behaviour and selective biocompatibility. In the process of radiation-co-cryogelation, opti-
mum radiation dose causes polymerization of monomers, which do not require addition
of any reaction initiator and activator for free-radical polymerization. However, simul-
taneous cryogelation allow the phase separation which leads to the formation of water
ice crystals (porozens) at sub-zero temperature. The optimum process parameters like
radiation dose, temperature, monomer’s concentration, physical/chemical molding, vol-
ume and incubation time, are providing suitable environment to fabricate an ideal porous
radiation-cryopolymerized cryogel (rpCryogel). This new approach is suitable to fabricate
scaffolds with controlled physico-chemical properties like variable pore sizes, pore inter-
connectivity and desired mechanical integrity and rheological properties by varying the
dose of γ-radiation and temperature at constant polymer precursor’s ratio. The scanning
electron microscopic observation of AAm and HEMA rpCryogels shows presence of in-
terconnected pore morphology having pore size range of 20 to 200 µm at different doses
of irradiation. Like classical cryogel, the rpCryogels showed similar behaviour of various
physico-chemical properties like hydraulic permeability (10´4 m4N´1s´1), density (1 to
1.5 g/cm3), water uptake kinetic (reach to equilibrium within 1 min) and water retention
capacity (more than 10 times its dry weight). Mechanical stiffness of rpCryogel showed a
steep decrease (10 times reduction in compression modulus) upon hydration in distilled
water suggesting its hydrophilic nature and soft material like property, which is preferable
in many bioprocesses. These monoliths can be compressed up to 70% of their original
length without showing permanent deformation presenting their high elastic behaviour.
Importantly, unlike classical cryogel which require approximately 18 h for synthesis, this
novel integrated approach requires only 3 h for the fabrication of rpCryogels in different
formats. The transitional changes between dry and wet state did not show change in its
physico-chemical properties, which describe long term storage stability of these rpCryogels
in dry state and wet state. Thus, the designing of elastic and macroporous monoliths by in-
tegrated controlled radiation and cryogelation process provides novel speedy approach for
the fabrication of macroporous rpCryogel for various bioengineering application and could
meet the supply requirement for commercial utilization. At present, we are investigating
the successive use of macroporous polymeric cryogels for biomolecules immobilization,
bioprocessing, tissue-engineering and environmental applications.
IAEA–CN–241–285 353
PA1
PA1-58 Session PA1, Wednesday 14:15 Vasquez
Kinetics of Free Radicals Decay Reactions in Cellulosic-Based
Heritage Materials Disinfected by γ-Radiation
P. Vasquez1, Y. Kodama1, R. J. Orlando1, R. H. Lazzari Garcia1, L. Otubo1, and
P. Souza Santos1
1Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), São Paulo, Brazil
Corresponding Author: P. Vasquez, pavsalva@usp.br
Disinfection by γ-radiation of cultural heritage artefacts and archived materials has been
successfully applied in recent years. Radiation processing used for cultural heritage dis-
infection has several advantages when compared to conventional methods (e.g., chemical
gases) mainly related to the safety, efficiency, reliability, capacity, process time and safety for
users and the environment. However, more research is still required to study undesirable
effects (side-effects) which may appear in sensitive materials as a function of the absorbed
radiation dose. Some conservators and restorers are frequently worried about possible
long-term effects in irradiated materials (post-effects). During the irradiation process, some
energetic and unstable chemical species called free radicals appear in the treated matter.
They disappear in different ways, interacting either with each other or with the artefact
compounds thus becoming responsible for disinfestation and irradiation side-effects.
The kinetics of free radical decay reactions depend on the absorbed dose, the properties
of irradiated material among others. In this study, contemporary paper samples were
irradiated using γ-radiation from 60Co with different absorbed doses. The absorbed dose
range was chosen taking into account the effective values to promote insect eradication,
fungal disinfection and sterilization. The decay kinetics of the cellulose free radicals induced
by irradiation was analyzed using electron paramagnetic resonance. Several spectra were
obtained at room temperature for each applied absorbed dose immediately after irradiation
as reference measurements. To understand the free radical decay process, additional spectra
were obtained for different decay times up to almost 50 days after irradiation. De-noising
treatment of the original obtained spectra signals were performed using wavelets. Free
radical populations, proportional to the spin concentrations, were found by integrating
the electron paramagnetic resonance signal curves. Comparison of spectra was done by
normalizing the calculated area corresponding to cellulose spin concentration, taking first
measurement after irradiation as 100%. Further analyses and calculations were made to
study the half-life and the kinetics models of the free radicals created. X-ray diffraction
was carried out to identify crystalline phases and the effect of ionizing radiation on the
crystalline structure of cellulose in paper. Scanning electron microscopy and scanning
electron microscopy energy dispersive spectrometry were performed to analyze structure
modifications induced by ionizing radiation, identifying cellulose fibre agglomeration zones
and to quantify chemical elements.
Results show that for the sterilization dose, 80% of the cellulose free radicals induced by
ionizing radiation disappear in almost 40 days and for disinfection dose in 8 days. It can be
concluded that if no modifications (side-effects) appear in the irradiated material after the
radical decay time, the material will stay stable for the remaining lifetime. Results showed
that the proposed method using electron paramagnetic resonance is suitably to study the
behaviour of radicals on cellulosic-based cultural heritage materials.
354 IAEA–CN–241–045
PA1
Vogt Session PA1, Wednesday 14:15 PA1-59
Feasibility of Using Irradiation to Degrade a Toxic Dye
Compound
M. V. Vogt1, M. C. Anessi1, and C. I. Horak1
1Comisión Nacional de Energía Atómica, (CNEA), Buenos Aires, Argentina
Corresponding Author: M. V. Vogt, vogt@cae.cnea.gov.ar
Crystal violet (CV), is widely used for dyeing cotton, silk and paper. It has carcinogenic
and mutagenic effects other than antimicrobial properties. The toxicity of this wastewater
represents a great risk to the ecosystem and must be treated before being discharged into
the environment. However, the complex aromatic molecular structures of CV make them
more stable and more problematic to degrade. Therefore, the removal of this synthetic
dye is of great concern because of the difficulty in treating such effluent by conventional
methods. In this study γ-radiation was investigated as a method for removing CV from
water. Absorbance, concentration, toxicity in eukaryotic cells and bacteria were analyzed.
The CV solution (300 mg{`) in glass bottles were irradiated in a 60Co γ-radiation facility.
Absorbance (1{10 dilution) and concentration were measured in a UV-vis spectrometer.
Cytotoxicity was tested in Vero cells after 24 h of treatment with different concentration
of CV solution irradiated. Cellular viability was determined with CV staining assays and
absorbance analysis at 570 nm. Cytotoxic concentration 50% (CC50) was calculated compar-
ing treated cells with cellular control. Antimicrobial susceptibility were analyzed using the
NCCLS guidelines for the microdilution method and minimum inhibitory concentration
(MIC) was defined.
The absorbed doses of CV solution were 1.1, 2.2, 3.1, 4.5 and 5.2 kGy, the absorption spectra
showed very small shift of the major peaks at about 300 nm and 580 nm but a reduction in
the height as the dose increase, indicating that the concentration of CV is reduced. However,
an small peak appears in the irradiated solution at 359 nm, indicating the possible formation
of an intermediate metabolite 4,41-bis(dimethylamino) benzophenone, as was reported by
other authors. The absorbed dose strongly affects the degradation of CV in water, at 1 kGy
66% was still remaining, and 20% with 5.2 kGy.
The cell viability results from CV 0 kGy demonstrated the severe inhibitory effects by
these chemicals; the CC50 was 8.8 mg{`. In contrast, the treatment of the solution with
the incremental doses of γ-radiation reduced the toxicity. The results showed that with
1.1 kGy the CC50 was 85.6 mg{` and 109 mg{` for the solution treated with 5.2 kGy. An-
timicrobial activity of the CV solution showed a reduction in a dose-based effect in all the
microorganisms tested. Staphylococcus aureusMIC increase from 1.5 mg{` to 37.5 mg{` for
the solutions 0 kGy and 5.2 KGy. Similar results were obtained with Bacillus cereus (6.25 to
100 mg{`) and Escherichia coli (50 to ą 150 mg{`). This study provided both a reference for
radiation degradation of CV without producing undesirable intermediate metabolites and
an alternative treatment processes for dye wastewater.
IAEA–CN–241–178 355
PA1
PA1-60 Session PA1, Wednesday 14:15 Weidauer
Toroidal Electron Source
A. Weidauer1, F.-H. Roegner1
1Electron Beam and Plasma Technology (FEP), Fraunhofer Institute for Organic Electronics, 01109 Dresden,
Germany
Corresponding Author: A. Weidauer, andre.weidauer@fep.fraunhofer.de
Electron beam sources are important for a very broad field of applications. Sterilization of
surfaces, irradiation of polymers for degradation, polymerization, grafting and cross-linking,
aswell as hardening of lacquers and disinfection of seed are an abstract of applicationswhere
electron beams are the state of the art. The penetration depth of accelerated electrons on
atmosphere is very limited. The electrons lose their energy on air. To apply an homogeneous
dose on 3D shaped products is difficult with existing line emitters or scanners with flat
window geometry. Current state-of-the-art is the usage of 2 or 3 line emitters to reach every
surface point on these kind of products.
FEP has developed an innovative toroidal-shaped electron emitter that emits electrons to
the centre of the source. The base of this source is the splitting of electron generation and
electron acceleration into two separate process steps. The first step is the generation of the
electrons: A plasma generates ions, the ions hit a cold aluminium cathode, thus electrons
are generated by ion bombardment of a cold cathode. In the second step the electrons are
accelerated by an negative potential on the cold cathode in direction to the electron exit
window. The first laboratory machines are designed in ring shape. The inner dimension on
atmosphere is 180 mm. Even more difficult shapes or are much taller inner dimensions are
possible.
The research and development of initial plasma and the generation of an homogeneous
electron beamare part of scientific investigations andwill be shownduring ICARST. FEPwill
present adjustment of dimensions, pressure and current for reach stable plasma conditions
and dosimetric analysis of treated products like 3D shaped SCF tubs that shows proof of
improvement in comparison to state of the art processes.
356 IAEA–CN–241–107
PA1
Zaouak Session PA1, Wednesday 14:15 PA1-61
γ-Radiation Induced Decolouration and Degradation on
Aqueous Solutions of Indigo Carmine Dye
A. Zaouak1, H. Jelassi1
1National Center for Nuclear Sciences and Technologies (CNSTN), Sidi Thabet, Tunisia
Corresponding Author: A. Zaouak, amirazaouak@gmail.com
The textile industry has long been one of the largest water users and polluters. Wastewater
released by textile industries contains toxic refractory dye stuff at high concentration. Most
of the dyes in the textile industry are non-degradable, therefore, effective treatment of dye
waste effluent has not been achieved by ordinary processes. Ionizing radiation has been
considered a promising process for the treatment of textile dye waste effluents.
In this study, the possibility of using γ-rays to degrade or decolourize a reactive dye in
water was investigated. A reactive dye (indigo carmine) in aqueous solutions was irradiated
at doses from 0.1 to 5 kGy at 47.62 Gy/min dose rate. The change of absorption spectra,
chemical oxygen demand (COD), and the degree of decolouration were examined. The
absorption bands at 248, 285 and 606 nm decreased rapidly with increasing irradiation dose.
The COD reduction for the dye solutions attended 90% at 5 kGy. Finally, a kinetic study
based on spectrophotometric measurements showed that the degradation process is pseudo
first order with an apparent constant kapp equal to 2.693{min.
IAEA–CN–241–152 357
PA1
PA1-62 Session PA1, Wednesday 14:15 Zimek
Electron Accelerator for R&D Study and Radiation Processing
Z. Zimek1, K. Roman1, and S. Dlugon1
1Institute of Nuclear Chemistry and Technology (INCT), Warsaw, Poland
Corresponding Author: Z. Zimek, z.zimek@ichtj.waw.pl
Upgrading of radiation facility located at the Institute of Nuclear Chemistry and Tech-
nology (ICHTJ) in Warsaw has been performed towards higher technical and economical
effectiveness, better operational characteristics suitable for radiation processing and re-
search programmes. The radiation facility located at ICHTJ was established in 1993, when a
10 MeV, 10 kW magnetron powered linear accelerator was installed in a separate building
and equipped with an appropriate conveyor system. During facility exploitation, spare part
availability and cost become a major problem in the maintenance of continuous service as
required by facility customers. The project objective, partly supported by the IAEA, was the
construction of a 10 MeV, 10–15 kW linear electron accelerator equipped with the microwave
source based on TH 2158 klystron (Thales, France), and standing wave accelerating section
(manufactured by NIIEFA, St. Petersburg, Russia).
The following stages of the design have been followed: electron gun, microwave system of
accelerator, auxiliary systems including klystron stand, pulse power supply stand, driving
generator stand and waveguide system, control, vacuum and water cooling systems. The
triode electron gunwith spherical impregnated cathode was selected as a source of electrons.
The gun parameters were optimized to meet requirements of standing wave accelerating
structure (distance between cathode and grid, distance between grid and anode, additional
beam focussing to obtain proper beam dimensions). The nominal parameters of accelerator
gun: 0.3 A; 50 keV; pulse repetition rate up to 300 Hz; pulse duration 20 µs. Fibre-optic
synchronization and triggering circuit based on pulse generator as reference source were
applied as triggering track of electron gun modulator, klystron modulator, and microwave
amplifier. Klystron modulator was designed on the based of semiconductor switch (cur-
rent load 1600 A, with voltage up to 18 kV). The modulator has been constructed to fulfil
requirement of TH 2158 klystron including safety (shutdown) circuit for protection against
current overload which may appear at semiconductor switch. The modulator is switched
off, and modulator load current falls to zero if value of overload current surpasses 900 A.
The microwave system of the accelerator is assembled from standard S-band components
including microwave isolator which was used to separate klystron against reflected wave
after breakdown occurs in accelerating section. SF6 isolation gas is used in waveguide
elements to improve isolation properties. The main accelerating section parameters are as
follow: electron energy 10 MeV, energy spectrum ˘2%, average beam power in the range
10–15 kW, pulse microwave poweră 5 MW, frequency 2856 MHz, electrical efficiency up to
58%, electron beam capture coefficient up to 85%, pulse output beam current 210 mA in
nominal conditions. Accelerator control system is equipped with Siemens microprocessors
and modules type Simatic S7-300, with communication channel Profibus and as SCADA
tool (supervisory control and data acquisition) WinCC. The vacuum system consists of
three ion vacuum pump type (pumping velocity 60 `{s) and turbomolecular vacuum pump
which is used to start ion pumps at certain vacuum level. Accelerator is installed in vertical
position and equipped with beam scanner 60 cm wide.
358 IAEA–CN–241–298
PA1
ICARST–2017
PA2: Posters PA2: Radiation Creation of Materials
from Fundamentals to Application
359
PA2
PA2-01 Session PA2, Thursday 14:15 Abdelrehim
Developing a Simple Method Using Ionizing Radiation to
Produce Polyacrylic Acid Based Nanoparticles
S. Abdelrehim1
1Egyptian Atomic Energy Authority (EAEA), Cairo, Egypt
Corresponding Author: S. Abdelrehim, ha_rehim@hotmail.com
The present work aims at synthesizing polyacrylic acid-based nano-particles using ionizing
radiation without surfactants. In this regard, acrylic acid in a solution in the presence
of polyaliphatic ester polymers like polycaprolactone and polylactic acid was exposed to
ionizing radiation at different dose rates to produce chemically cross-linked polyaliphatic
ester /PAAc nanoparticles. Particle size and swellability of the prepared nanoparticles can
be controlled by irradiation dose, irradiation atmosphere, and feed copolymer composition
and concentration. Characterization of the prepared nanoparticles including morphological
structure, pH sensitivity and rheological characteristics was carried out using dynamic light
scattering (DLS), viscometry, transmission electron microscopy (TEM) and atomic force
microscopy (AFM) techniques.
360 IAEA–CN–241–390
PA2
Aguilera-Corrales Session PA2, Thursday 14:15 PA2-02
Synthesis by γ-Radiation and Characterization of
Poly(Vinylpyrrolidone) Nanogel
Y. Aguilera-Corrales1
1High Institute for Applied Technologies and Sciences (InSTEC), Havana, Cuba
Corresponding Author: Y. Aguilera-Corrales, yuri@instec.cu
The synthesis of polyvinylpyrrolidone (PVP) nanogels by ionizing radiation techniques
(γ irradiation), for their evaluation as potential system of drug delivery was the aim of this
research. Solutions were prepared with water purified by distillation and in order to remove
any dust particles and/or polymer aggregates, solutions were filtered subsequently through
filters of 0.45 and 0.22 µm pore size. The γ-irradiation was carried out with a panorama
60Co source at dose ranging from 5 to 25 kGy.
Particularly, the polyvinylpyrrolidone nanogels can be obtained by γ-radiation, based not
on polymerization, but on intramolecular cross-linking of polymers chains, in aqueous
solutions. The nanogel characterization was performance by electron microscopy (TEM,
SEM), DRX, spectroscopy (UV-visible and IR), light scattering, viscosimetry, delivery of an
active agents and cytotoxicity trials.
The results showed that in dependence on the polymer concentration and the rate dose two
different cross-linking reactions can take place. Irradiation experiments at room temperature
in diluted solution with further increasing of the radiation dose lead to the formation of PVP
nanogels due to an intramolecular cross-linking reaction. By using both light scattering and
TEM the PVP nanogels were measured, these showed a size distribution of 50.10 nm. They
have lots of advantages over conventional systems since they enhance the delivery, extend
the bioactivity of the drug by protecting them from environmental effects in biological
media, show minimal side effects, demonstrate high performance characteristics, and are
more economical since minimum amount of expensive drugs are used.
IAEA–CN–241–169 361
PA2
PA2-03 Session PA2, Thursday 14:15 Aktar
Application of γ Radiation and Physicochemical Treatment to
Improve the Bioactive Properties of Chitosan Extracted from
Shrimp Shell
J. Aktar1, M. Z. Hasan2, T. Afroz1, H.-O. Rashid3, and M. K. Pramanik2
1Department of Zoology, Jahangirnagar University, Dhaka 1342, Bangladesh
2Microbiology and Industrial Irradiation Division, Institute of Food and Radiation Biology,
Bangladesh Atomic Energy Commission (BAEC), Dhaka, Bangladesh
3Bangladesh Atomic Energy Commission (BAEC), Dhaka, Bangladesh
Corresponding Author: J. Aktar, jesminju@gmail.com
The aim of this study is to improve the different bioactive properties of chitosan extracted
from chitin by different physicochemical treatments including γ-radiation. Chitin was
prepared from shrimp shell upon deproteination, decalcification and oxidation with 4%
NaOH, 4% HCl, and 2% H2O2 respectively. To find out a more efficient, economically
reasonable and time saving chitosan extraction method other than existing methods, eight
different physicochemical treatment methods (designated as A, B, C, D, E, F, G and H)
varying different parameters were applied for chitosan extraction. Chitosan produced by
these extraction methods were compared with commercially available chitosan and assessed
with respect to degree of deacetylation (DD-value), molecular weight, antimicrobial activity
and solubility. DD-value of chitosan extracted by method A, B, C, D, E, F, G and H were
75.0˘ 0.28%, 92.0˘ 0.34%, 81.0˘ 0.51%, 89.0˘ 1.34%, 69.0˘ 0.05%, 87.0˘ 0.35%, 82.0˘
1.4% and 92.0˘ 0.92% respectively whereas the DD-value of the commercially available
product was „ 75.0%. Viscosity-average-molecular-weights were found 1.77ˆ 105 ˘ 0.28,
1.6ˆ 105 ˘ 0.50, 1.82ˆ 105 ˘ 0.46, 1.19ˆ 105 ˘ 0.39, 2.25ˆ 105 ˘ 0.39, 1.41ˆ 105 ˘ 0.67,
1.77ˆ 105 ˘ 0.28 and 1.16ˆ 105 ˘ 0.69 Dalton, respectively. Antimicrobial activity of all
chitosan samples was found insignificant and all the samples could be dissolved completely
at minimum 0.5% of acetic acid solution.
For further quality improvement, chitosan with highest DD value (prepared by method B)
was irradiated with different doses (5.0, 10.0, 15.0 and 20.0 kGy) of γ-radiation and again
assessed for different quality parameters. Though no significant changes in DD value of
chitosan was observed upon irradiation, it causes significant changes in the molecular
weight of chitosan samples. Molecular weight gradually decreased as the radiation dose
increased. Molecular weight of the samples treated with the radiation doses of 5.0, 10.0,
15.0 and 20.0 kGy were 1.786 ˆ 103, 1.518 ˆ 103, 1.134 ˆ 103 and 1.046 ˆ 103 Dalton,
respectively. Radiation treatment of chitosan samples also increased the antimicrobial
activity in concentration dependent manner. One and half (1.5%) percent chitosan solution
treated with a radiation dose of „ 10.0 kGy showed highest antimicrobial activity.
Repeated alkali treatment (20 M NaOH) and autoclave for 30 minutes was found to be
the best extraction method and irradiation of chitosan solution with 5.0 to 10.0 kGy fur-
ther increased its bioactive characteristics including enhanced antimicrobial and solubility
properties.
362 Presenter: M. K. Pramanik IAEA–CN–241–301
PA2
Anessi Session PA2, Thursday 14:15 PA2-04
Predicting the Behaviour of a Biomaterial as Bone Replacement
M. C. Anessi1, A. G. Flores2, G. A. Juarez3, N. Santoro4, L. Romero4, and C. I. Horak5
1Laboratorio de Biotecnologia, CNEA, Argentina
2Laboratorio de Materiales de Fabricacion de Aleaciones Especiales, CNEA, Argentina
3Departamento de Tecnología de Aleaciones de Circonio, CNEA, Argentina
4Laboratorio de Polimeros, CNEA, Argentina
5Departamento Procesos por Radiación, CNEA, Argentina
Corresponding Author: M. C. Anessi, anessi@cae.cnea.gov.ar
When an artificial material is implanted into the body, a fibrous capsule may appear sepa-
rating the material and the tissue. But when the material is bioactive, this capsule doesn’t
appear, and the biomaterial conducts the formation of an interfacial bonding between the
implantable device and living tissues, called apatite. The bioactivity is defined as the bio-
logic positive answer in a determined biological environment (human body or a simulated
human environment). To evaluate the feasibility of new biomaterial development, it is
important to know their bioactivity because this may predict the bone-forming ability of
an implantable material for bone tissue replacement. Another property that helps in this
prediction is the bio-evaluation of these materials, where the initial evaluation involves the
cytotoxicity, which determines the possible toxicity produced on cells by the device, and
also considers the nature of body contact and duration of contact. The objective of this
study was to analyze the bioactivity and cytotoxicity of a bone replacement biomaterial,
consisting of high density polyethylene (HDPE) with a load of hydroxyapatite (HA).
Biomaterial sampleswere prepared by extrusion as flat and rectangular specimens composed
of HDPE and different loads of HA (100:0; 90:10; 70:30; 50:50); and they were irradiated
with different γ-radiation doses (15, 30 and 45 kGy). Radiation is used to promote cross-
linking to minimize wear under physiological conditions, and for sterilization. To assess
the bioactivity a blood similar solution was used (ISO 23317). The samples were incubated
for 30 days. Their surfaces were analyzed by scanning electron microscopy (SEM) and
the crystallinity of the HA produced on the surface was determined by X-ray diffraction
(XRD). Citotoxicity was conducted using the MTT assay determining the cellular viability
(ISO 10993-5). The results obtained by XRD and SEM showed an homogeneous formation
of HA crystals, without differences between compositions and irradiation doses. Only in
the samples 100% HDPE did not present apatite crystals on its surface. All samples showed
viability higher than 70%, indicating that no cytotoxicity was generated in any condition.
Based on the obtained results, the biomaterial samples composed of HDPE and HA were
bioactive and non-cytotoxic. Therefore the biomaterial seems to be a good bone tissue
implant. These studies carried out, showed to be very useful, as a preliminary or screening
step, before starting with the clinical trials. They can reduce costs, when the composition or
the process has to be changed before going forward. On the other hand, when the results
are satisfactory, they can predict that these materials will generate an appropriate beneficial
cellular or tissue response in that specific situation. It has been demonstrated that materials
that possess favourable hydroxyapatite layer formation integrate more successfully in the
body. Additional tests are underway on this biomaterial to definewhich the best composition
is and which is the optimal radiation dose that generates a simil-bone biomaterial, with
similar mechanical properties, and with minimal degradation debris.
IAEA–CN–241–133 363
PA2
PA2-05 Session PA2, Thursday 14:15 Calina
Electron Beam Synthesis of Inulin Hydrogels Extracted from
Helianthus Tuberosus L.
I. C. Calina1, A. Scarisoreanu1, C. Vancea1, M. Popescu2, N. Bordei2, G. Craciun1,
E. Stancu1, E. Badita1, and M. Demeter1
1National Institute of Research & Development for Laser, Plasma and Radiation Physics, Romania
2S.C. Hofigal, Romania
Corresponding Author: I. C. Calina, calina.cosmin@inflpr.ro
Obtaining hydrogels from various classes of natural polymers has undergone significant
growth over time especially for applications in the biomedical field. Hydrogels made
from natural polymers have the advantage of being biocompatible and biodegradable. In
this context, an important role is played by inulin-based hydrogels, which is a natural
polysaccharide. In our study we describe a method for extracting inulin from Jerusalem
artichoke (Helianthus tuberosus L.) while current methods imply obtaining inulin form the
root of chicory (Cichorium intybus).
Inulin form Jerusalem artichoke was supplied by S.C. Hofigal Export Import S.A. The
concentrated inulin extract was obtained after three consecutive extractions in vacuum.
The Ar-saturated inulin extract was irradiated with an electron beam at the dose rate of
2–4 kGy/min up to 25 kGy in “paste-like” conditions and in the presence of tannic acid
(TA) and glycidyl methacrylate (GMA). Sol-gel analysis was performed in order to deter-
mine the polyssachride-gel conversions ratio, the radiochemical yield of cross-linking and
degradation. In order to follow the formation of a 3D hydrogel network and its composi-
tion, dynamic rheological measurements and FT-IR analysis were performed. The swelling
capacity was determined in deionized water and phosphate buffer solution pH“7.4 at 37˝C.
The resulting gel fraction is dependent on the absorbed dose and on the increasing con-
centrations of TA and GMA. The value of radiochemical cross-linking yield was larger
than degradation yield. The rheological measurements revealed the obtaining of a gel with
G1 ą G2, where the G1 value has decreased with dose. The maximum value of swelling
capacity for the inulin hydrogel was found to be around 10 000%, with smaller values for
gels that were swollen in phosphate buffer solution. This gel offers a promising route of
administration for various drugs with anti-inflammatory and analgesic properties. This
study will be continued by embedding natural extracts obtained from arnica, pepper, aloe
vera and Echinacea, in the inulin hydrogel, in order to obtain a product with applicability
in treatment of chronic colon disease.
364 IAEA–CN–241–252
PA2
Cardoso Session PA2, Thursday 14:15 PA2-06
Recycled HDPE/Vulcanized EPDMMixtures Obtained by
Irradiation Processes
J. Cardoso1, A. Geraldo1, and E. Moura1
1Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), São Paulo, Brazil
Corresponding Author: J. Cardoso, cardosorjessica@gmail.com
Recycling polymers process includes techniques that present solutions to the problem
of plastic waste in the environment. This process is important to improve the economic
sector in many countries, like cooperative societies. Primary recycling is related to the
reuse of plastic waste directly from the production site in the industry, that carry on some
advantages besides the low cost involved in the reuse of this waste: the raw material is free
from dust of many kinds (metals, different powders and plastics). Among this polymeric
waste, packaging dominates this scenario, covering 62.2% of the total, where polyolefins
account more than 50% of the packaging production. In the same way, the recovering of
sulfur-cured rubber contribute to release the environment from this almost non-degradable
rubber. The goal of this work is to produce an alternative recycled product composed
by mixing twenty-times reused HDPE (by primary recycling process) with vulcanized
EPDM rubber. The twenty-times recycled thermoplastic was reached by extrusion, which
intention was to simulate a polyolefin like a scrap. The EPDM rubber was fragmented and
incorporated to the thermoplastic matrix in proportions of 1% and 5% w/w, from both kinds
of rubber, like received and after a thermal treatment. One of the thermal treatment of rubber
consisted in an oven ageing in the temperature of 100˝C; the other was a simultaneous
heating under irradiation process by electron beam at 130˝C and at 100 kGy absorbed
dose (at 22.4 kGy/s dose rate). The final mixture was obtained by injection molding and
specimens from injection process were γ-irradiated at 50 kGy and at 100 kGy. Mechanical
analysis of stress-strain, infrared FTIR spectra and thermogravimetric degradation were
performed to evaluate the final product. The obtained product showed heterogeneous; the
rubber without thermal treatment was better incorporated to thermoplastic matrix and the
irradiated samples present mechanical resistance that suggests this new material intended
to be viable to industrial use.
IAEA–CN–241–409 365
PA2
PA2-07 Session PA2, Thursday 14:15 De Silva
Determination of the Radiation Dose Required to Obtain
Desired Viscosity Average Molecular Mass Using Commercially
Available Chitosan and Signification of this Technique in its
Applications
K. R. C. De Silva1, A. K. Ratnayake1, S. Y. Ratnayake1, R. M. M. P. Ranaweera1,
S. S. Kulathunge1, C. K. Dissanayake1, and S. D. M. Chinthaka2
1Sri Lanka Atomic Energy Board, Colombo, Sri Lanka
2University of Sri Jayewardenepura, Gangodawila, Nugegoda, Sri Lanka
Corresponding Author: K. R. C. De Silva, ruwan@aeb.gov.lk
Radiation processed chitosan polymers are used in many applications in the field of agricul-
ture such as plant growth promoters, elicitors, fungicides and self-life extending coatings for
fruits, etc. Radiation or chemical degradation techniques or a combination of both methods
can be used to convert higher molecular masses of chitosan to its different low molecular
masses. The applicability of the chitosan in the above applications highly depends on the
molecular weight of chitosan. However, viscosity average molecular masses of commercially
available chitosan (CAC) show huge variations and these variations arise due to the use
of different techniques in the extraction process. This variation of the molecular masses
of the CAC makes it difficult to determine the correct radiation dose to obtain the desired
molecular weight. The main objective of this study is to construct a correlation between the
variation of viscosity average molecular mass of CAC samples versus irradiated doses. The
above correlation enables the determination of the radiation dose required to get the desired
molecular weight from a known initial molecular weight. The viscosity average molecular
mass is the key factor of the performance of the products developed using chitosan.
CAC samples with similar degree of deacetylation (DDA) and various molecular masses
were irradiated at different radiation doses using GC-5000 Gamma Cell under 3.4 kGy/h
dose rate. The viscosity average molecular mass of these irradiated samples were analyzed
using capillary viscometric method. AVS 470 Visco system with a standard solvent system
(0.25 M CH3COOH/ 0.25 M CH ˝3COONa at 25 C) and Mark-Houwink-Sakurada equation
were used for the determination of viscosity averagemolarmasses. The relationship between
the varying viscosity average molar masses versus absorbed dose was constructed using
regression analysis and desired molecular weight was obtained using this relationship.
Oligo chitosan with selected molecular masses are used in the production of some agro-
products and the above technique can be used as an initial step of the production of oligo
chitosan with required molecular weight using CAC. Oligo chitosan can be produced
using a combination of chemical and γ-irradiation techniques (synergistic technique) in
aqueous media. However, a standard procedure cannot be followed in the production of
oligo chitosan due to the dissimilarities of the molecular masses of CAC. Therefore, a fixed
initial molecular weight (compatible with existing standard procedure) should be produced
using CAC in order to follow a standard procedure based on the synergistic technique. The
regression curve developed under this study was used to find out the required dose to
produce fixed molecular weight using CAC. Therefore, the procedure developed through
the above study can be utilized to derive the fixed low molecular weight chitosan to follow
the standard procedures used in pilot and commercial scale productions of agro products
which are based on oligomer/low-molecular-weight chitosan.
366 IAEA–CN–241–167
PA2
Eisawy Session PA2, Thursday 14:15 PA2-08
The Effect of Radiation Environment on Electrical Insulation
Materials
E. Eisawy1
1National Center for Radiation Research and Technology (NCRRT), Nasr City, Cairo, Egypt
Corresponding Author: E. Eisawy, eisawy_ez@yahoo.com
Due to recent renewed interest in reactor safety andmany reactors approaching end of useful
lifetime, emphasis on durability of power and instrumentation electrical InsulatingMaterials
is growing. While current materials have shown suitable radiation tolerance in lab testing,
combined effects of radiation, temperature, andwater at normal or abnormal conditions have
led to cable failures. Effects of radiation types and dose rates on selected cable insulating
materials have been studied. Effects of dose-rate temperature during radiation on service
endurance are considered. Dielectric materials used to fabricate various parts of electrical
equipment systems, nuclear and electronic devices often operate in ionizing radiation fluxes,
problems of radiation resistance and changing of insulatingmaterials and devices are urgent.
It is necessary to develop ways to improve the radiation resistance.
Radiation damage to dielectric and insulating materials is a function of temperature and
atmospheric conditions as well as the radiation environment. Many materials are more
resistant to radiation in the absence of oxygen or moisture and at lower temperatures.
Because of this influence of environmental conditions it is impractical to attempt to compile
detailed information that would be directly applicable to all circuit requirements and
environmental conditions. The fabrication method used by the manufacturer can also be a
factor in the amount of damage that occurs from radiation. Both temporary and permanent
changes occur in the characteristics of organic insulating and dielectric materials as a result
of exposure to a radiation environment. Enhancement of the electrical conductivity is the
most important of the temporary effects with increases of several orders of magnitude
being observed. The conductivity increases exponentially in response to ionizing radiation
until it reaches equilibrium at a value that is determined by the rate of exposure and
ambient temperature for a specific material. Following the termination of the irradiation
the induced conductivity gradually decreases. Other temporary effects, in addition to the
enhanced conductivity, are a reduction in breakdown and flashover voltages, increases in
AC loss characteristics, and variations in dielectric constants. These changes in electrical
characteristics, however, are often not large enough to prevent the use of the insulators in a
radiation environment, particularly if allowances are made to minimize their effect on the
circuits’ performance.
Permanent effects of radiation on organic insulating materials are normally associated with
physical changes, including decreases in hardness, tensile strength and melting point, and
greater solubility. This physical degradation in the advanced stages is disastrous in that
the insulating material breaks, crumbles, or powders thus losing structural integrity and
causing failure. Changes in dissipation factor and insulation resistance have also occurred
as permanent effects, but they are normally quite small and offer few problems except in the
most uncommon applications. A comparison of the relative radiation resistance of organic
insulating materials to permanent effects is presented. Gas evolution, a secondary reaction
that occurs when organic insulators are irradiated, is a problem because of pressure buildup
in confined enclosures.
IAEA–CN–241–105 367
PA2
PA2-09 Session PA2, Thursday 14:15 El-Sawy
Radiation Synthesis of Acrylic Acid onto
Poly(tetrafluoroethylene-perfluorovinyl ether) Film: Chemical
Modifications and Electrical Conductivity
N. El-Sawy1, M. Ghobashy1, A. Elbarbary1, and H. Hosni1
1National Center for Radiation Research and Technology (NCRRT), Nasr City, Cairo, Egypt
Corresponding Author: N. El-Sawy, naeem.elsawy@yahoo.com
Graft-polymerization of acrylic acid (AAc) monomer onto poly(tetrafluoroethylene-per-
fluorovinyl ether) copolymer film was carried out using γ-irradiation techniques to synthe-
size graft copolymer membranes PFA-g-PAAc (PFA-COOH). The effect of the irradiation
dose on the degree of AAc grafting onto PFA films was investigated. The results showed
that the degree of grafting increases with increasing irradiation dose. The grafting yield 19,
47 and 73% of the prepared films [PFA-COOH] were selected for chemical modification by
reaction with aniline to produce modified membrane [PFA-CO-NH-ph] followed by sul-
fonation reaction to introduce sulfonic acid (SO3H) groups to get other modified membrane
[PFA-CO-NH-ph-SO3H]. The chemical structures of the grafted and modified membranes
were characterized by FT-IR, XRD, and SEM techniques.
It is of particular interest to measure the AC conductivity of flexible chemical modified
membranes as a function of grafting degree. The modified membranes of the grafting
yield 40 and 80% exhibited AC electrical conductivity. The electrical conductivity increases
with increasing grafting degree and by chemical modification especially aniline modified
grafted films. The electrical conductivity of modified membranes considered for use as
semiconductor materials in fuel cell applications.
368 IAEA–CN–241–341
PA2
Farahat Session PA2, Thursday 14:15 PA2-10
Sorption of Iodine on Ion Exchange Resins
N. Farahat1, N. Kamel1, and M. Shehata2
1Egyptian Atomic Energy Authority (EAEA), Cairo, Egypt
2Cairo University, Giza, Egypt
Corresponding Author: N. Farahat, nohasammy@yahoo.com
One of the most important applications of radiation in the field of chemistry is the modifi-
cation of polymeric species for the purpose of separation and purification of radioactive
species is radiation induced graft polymerization (RIGP) and emulsion polymerization
both in which various factors affect the polymerization process most important of which
is the radiation dose. The monomer glycidyl methacrylate (GMA) has been polymerized
by radiation induced graft polymerization on polyethylene tubes with optimum solvent
concentration, radiation dose, radiation time, and also GMA has been polymerized by
radiation emulsion polymerization influenced by the irradiation dose rate and the type of
emulsifier namely TWEEN 80 in this study. The GMA is a significant monomer due to the
presence of the epoxy group which can further modified for purpose of ion exchange.
Ion exchange is the optimum technique for treatment of radioactive wastes and or purifi-
cation of produced radioactive isotopes especially for medicinal uses, so the development
of lost cost ion exchange resins that are capable of adsorbing ions in interest from high
volumes of effluent on the least amount of adsorbent with high adsorption capacity and
low amount of solid waste.
Radioactive isotope production facilities have been established all around the world for
manufacturing of radioisotopes for pharmaceutical uses either by neutron activation or by
fission of uranium as 99Mo, 99mTc and 131I.
The PolyGMA prepared by both techniques was modified using triethyl amine for embed-
ding with tertiary amino groups for acting as an anion exchanger for purification of 131I
produced from other fission products. A comparative study for the adsorption of 131I in the
form of iodide between the synthesized resins and four commercial anion exchange resins
namely (Biorex 5,Dowex 1–8x (20–50 mesh), Dowex 1–8x (100–200 mesh) and Dowex 21) by
the radiotracer technique using radioactive 131I manufactured locally. Characterization of
different stages of anion exchange was performed by Fourier transformation infrared and
scanning electron microscope incorporated with EDX, scanning electron microscope and
EDX image of PolyGMA in iodide form.
The polyGMA prepared by TWENN 80 showed no adsorption for radioactive iodine, while
the polyGMA prepared by radiation induced graft polymerization on polyethylene tubes
showed adsorption of about 30% which was verified with infrared and scanning electron
microscope and EDX all resins obeyed the pseudo second-order rate of reaction indicating
chemical sorption of iodide ions, and obeyed Langmuir and Freundlich equations.
IAEA–CN–241–221 369
PA2
PA2-11 Session PA2, Thursday 14:15 Ferreira
Verde
Distinct Polymeric Based Materials Prepared/Functionalized by
γ-Irradiation for Biomedical Applications and Roman Mosaics
Preservation
L. M. Ferreira1, M. H. Casimiro1, J. J. H. Lancastre1, A. P. Rodrigues1, S. Cabo1,
L. C. Alves1, A. N. Falcão1, S. R. Gomes1, G. Rodrigues2, F. M. A. Margaça1, J. P. Leal1,
J. Coroado3, V. Hipólito Correia4, and M. F. Araújo1
1Centro de Ciências e Tecnologias Nucleares (C2TN), Instituto Superior Técnico (IST), Lisbon, Portugal
2Centro de Ecologia, Evolução e Alterações Ambientais, Universidade de Lisboa, 1600-276 Lisboa, Portugal
3Instituto Politécnico de Tomar, Quinta do Contador, Estrada da Serra, 2300-313 Tomar, Portugal
4Museu Monográfico de Conimbriga, 3150-220 Condeixa-a-Nova, Portugal
Corresponding Author: L. M. Ferreira, ferreira@ctn.tecnico.ulisboa.pt
Polymeric based materials are being successfully prepared, modified or functionalized
by ionizing radiation processing techniques targeting an increasing number of specific
applications in different areas. We have been particularly focussed in two reactional systems:
1. Chitosan based copolymeric biocompatible and biodegradable matrices to be used as
skin scaffolds for tissue regeneration processes; and,
2. PDMS-Silica ormosils (organically modified silicates) hybrid materials for medical
applications (bioactive component for bone substitution, reparation and consolidation
for orthopedic and dental surgeries) and for the consolidation of ancient Roman
mosaics (additive with biocide activity for the composite materials used in ancient
mosaic panel conservation processes).
Regarding chitosan based copolymeric biocompatible and biodegradablematrices, amethod-
ology involving freeze-dry of (co)polymeric solutions followed by γ irradiation from a 60Co
source was tested. In order to compare the performance of matrices concerning cell-matrices
interaction, the effect of matrices content in poly(vinyl alcohol) and gelatin was evaluated
in terms of matrices’ structural properties and cellular viability. Results evidence that for
the same radiation dose matrices’ composition can be used to tailor the matrices’ surface
in terms of porosity/roughness. Moreover, in vitro tests revealed that cells adhered and
proliferated in all irradiated matrices.
Concerning the preparation of hybrid materials by γ-irradiation, we have been investigating
the system PDMS-TEOS-PrZr (polydimethylsiloxane, tetraethylorthosilicate and zirconium
propoxide, respectively) in different conditions. Materials are prepared by direct energy
deposition on a mixture of PDMS silanol terminated (33 wt% fixed content), TEOS and
a minor content of PrZr that varied from 1 to 5 wt%, in a closed system under nitrogen
atmosphere, using γ-radiation from a 60Co source. The samples, dried in air at room
temperature, are bulk, flexible, transparent and nanostructured. Depending on the polymer
Mw and on the amount of PrZr, it is possible to tailor the size and distribution of the oxide
regions as so the hybrid porosity. Results obtained evidence, although relatively low, their
natural bioactivity and biocide activity. The introduction of new components in the hybrid
formulation to improve these properties seems to be effective, without compromising their
370 IAEA–CN–241–257
PA2
Ferreira Session PA2, Thursday 14:15 PA2-11
natural affinity and compatibility with the materials to which they are intended to “work
together”. Preliminary results shows good perspectives for their intended use.
IAEA–CN–241–257 371
PA2
PA2-12 Session PA2, Thursday 14:15 Garcia-Uriostegui
Synthesis of Cross-Linking Films Based of 3-(Trimethoxysilyl)
Propyl Methacrylate Silanized Xanthan Gum/Lignin and their
Cross-Linking by γ-Radiation, to Potential Application and
Films Packing
L. Garcia-Uriostegui1, A. Ortega2, and E. Delgado1
1Departamento de Madera Celulosa y Papel, Universidad de Guadalajara, Zapopan, Jalisco 45110, Mexico
2Instituto de Ciencias Nucleares, Universidad Nacional Autónoma de México (UNAM), 04510 Ciudad de
México, Mexico
Corresponding Author: L. Garcia-Uriostegui, lgarciaur@conacyt.mx
The production of biodegradable and edible films based on biopolymers has attracted
attention and represents one of the most advanced challenges in the field of food packaging
and coating. Polymers derived from natural products offer the greatest opportunities as
component of edible films since they are biodegradability and environmental friendly r1s.
Xanthan gum has been used in a wide variety of foods (in many low fat food systems
due to its water binding capacity) for a number of important reasons, including emulsion
stabilization, temperature stability, compatibility with food ingredients and its pseudo-
plastic rheological properties r2s. Xanthan gum is classified E415 in the European List of
Permitted Food Additives. According to JECFA (Joint WHO/FAO Expert Committee on
Food Additives), it has the status of ADI-nonspecified (Acceptable Daily Intake), i.e., no
quantitative limitation is stated, and, as such xanthan gum is recognized as a non-toxic
additive for human consumption. Lignin, a natural biopolymer, mostly derived from wood,
is an enormous and renewable reservoir of latent polymeric materials and aromatic chem-
icals. Due to their very complex structure, lignins are amorphous polymers with rather
limited industrial use. They are usually seen as waste products of pulp and paper industry
and often used as fuel for the energy balance of the pulping process r3s. Unfortunately, the
use of biopolymers as food packaging materials has drawbacks such as poorer mechani-
cal, thermal, and barrier properties as compared to the conventional non-biodegradable
materials made from petroleum. The incorporation of nanofillers such as silicate, clay, and
titanium dioxide (TiO2) to biopolymers may improve not only the biopolymers’ mechanical
and barrier properties but also offer other functions and applications in food packaging
such as antimicrobial agent, biosensor, and oxygen scavenger r4s.
In this work, the xanthan gum/lignin mixture was silanized with 3-(trimethoxysilyl) propyl
methacrylate, and consequently cross-linking by γ-radiation. The best conditions to pre-
pared hybrid biofilms were 95{5 ratio of xanthan gum/lignin, 5 wt% of organosilane at
20 kGy at 5 kGy/h of dose and dose rate respectively. By FTIR-ATR and NMR spectroscopy
was possible confirm the silanized reaction. The morphological aspect and size dimension
were determined by SEM and TEM. The thermal behaviour was analyzed by DSC and TGA.
References
r1s N. Akdeniz, S. Sahin, and G. Sumnu, J. Food Eng., 75, 522–526 (2006).
r2s F. Jiangyang, et al., Carbohydr. Polym., 73, 241–247 (2008).
r3s J. K. Saini, R. Saini, and L. Tewari, Biotech, 5, 337–353 (2015).
r4s J. W. Rhim, Carbohydr. Polym., 86, 691–699 (2011).
372 IAEA–CN–241–218
PA2
Ge Session PA2, Thursday 14:15 PA2-13
Monodispersed Polypyrrole Nanoparticles Prepared via Water
Padiolysis and their Photothermal Therapy on Cancer Cells
X. W. Ge1
1University of Science and Technology of China (USTC), Anhui Sheng, Hefei Shi, People’s Republic of China
Corresponding Author: X. W. Ge, xwge@ustc.edu.cn
The combination of NIR photothermal therapy and chemotherapy is considered as the
promising technique for the future cancer therapy r1s. The key point for this technique
is the design and synthesis of photothermal agents with high-efficiency photothermal
effect and high chemical drug loading capacity r2s. Herein, submicron-sized raspberry-like
hollow-structured polypyrrole microspheres (H-PPy) were easily prepared through the in-
situ polymerization of pyrrole on monodispersed polystyrene (PS) template microspheres
with a diameter of 220 nm, followed by the chemical etching of the PS templates. The
prepared H-PPy microspheres show rapid and remarkable photothermal effect in water
under the irradiation of NIR laser (808 nm) only for 5 min. Further, a model small molecular
drug, (S)´p`q-camptothecin (CPT), were loaded into the void core by a simple dispersion-
permeation process through the micro-pores on the raspberry-like PPy shell, with a load
capacity of 0.14 mg/(mgH-PPy). TheMTT assay and the in vitro NIR-laser triggered release
behaviour indicated that the pure H-PPy microspheres have good biosafety, but the release
of loaded CPT in H-PPy microsphere can be achieved with remarkable spatial/temporal
resolution after NIR laser irradiation, which results in the excellent synergistic effect of
photothermal and chemical ablation onHeLa cells, as proved by the fluorescencemicroscopy.
This work provides a convenient synthesis of a promising cancer therapy agent with high
drug-loading capacity and efficient NIR light photothermal effect, which can perfectly
achieve the synergistic NIR photothermal therapy and chemotherapy of PPy microspheres.
References
r1s K. Dong, et al., Adv. Mater., 25, 4452–4458 (2013).
r2s J. P. Yang, et al., Chem. Mater., 25, 3030–3037 (2013).
IAEA–CN–241–139 373
PA2
PA2-14 Session PA2, Thursday 14:15 Geraldo
Obtention and Characterization of γ-Irradiated Recycled
HDPE/EPDDM Blends
A. Geraldo1, A. Geraldo1, E. Moura1, and L. Gabriel1
1Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), São Paulo, Brazil
Corresponding Author: A. Geraldo, aureabeatriz.cerqueirageraldo@gmail.com
Elastomeric materials have specific properties that allow the development and use of a
variety of products. The application of elastomeric compounds in the automotive industry
has increased considerably; due this, high volume of parts are disposal and among these,
thermosetting materials, that are not easily recyclable. High density polyethylene (HDPE) is
a commodity material with a wide range of uses in the industry. What make this polymeric
material so interesting to the market are its unique properties such as good conformability,
high resistance to heat and chemicals, and a relative low cost. Another characteristic for
this material is its good reprocessability, which is the ability of being recycled many times.
Thus, the environmental impact of both materials is evident, thereby promoting essential
damage.
In the present work the HDPE matrix has been recycled four times from original substrate
andmixed to EPDM rubber not vulcanized in proportions from 1% to 10%. The γ-irradiation
process was applied at 50 kGy and 100 kGy in both original and recycled blend samples;
in this way, mechanical properties and morphologic characteristics were evaluated. The
results shown EPDM in quantities of 1% bring high tensile strength and yield strength to
recycled non-irradiated blends compared to higher concentration of 10%, that present high
impact resistance. Irradiation process applied to these samples carried an increase in these
parameters and the recycled blends presented higher tensile strength values than pristine
HDPE samples. Blends are homogeneous and presented no specific morphologic aspects
that suggests HDPE and EPDM are miscible and compatible components; crystallinity is
higher in low EPDM content blend and at a dose value of 50 kGy the crystallinity reached
the maximum value of 79.5% compared to 72.2% for pristine HDPE. These results suggest
irradiated blends formed by recycled HDPE with 1% of EPDM present high viability for
industrial use due its high mechanical performance compared its low production cost.
374 IAEA–CN–241–269
PA2
Ismail Session PA2, Thursday 14:15 PA2-15
γ-Radiation Enhancement of Photocatalytic Activity of
Conducting Polyaniline-TiO2 Nanocomposites for Degradation
of Methyl Orange Dye under Visible Light Irradiation
S. Ismail1, E. Hegazy1, N. Degheidy1, and H. A. Abd El-Rehim1
1Egyptian Atomic Energy Authority (EAEA), Cairo, Egypt
Corresponding Author: S. Ismail, ismaiel_sahar@yahoo.com
Environmental pollution on a global scale, as well as the lack of sufficient clean energy
sources, have drawn much attention to the need for developing ecologically clean chemical
technology, materials, and process. Synthetic dyes are used almost in all branches of the
consumer goods industry. About 10 000 tons of dyes are produced per year. Inevitably,
there are dye losses (approximately 12% of used amount) during manufacturing and pro-
cessing operations. The effluents from these operations are usually highly coloured, toxic,
carcinogenic or mutagenic. As the most of the synthetic dyes are resistant to light or other
degradative environmental conditions, it is necessary to remediate these effluents before
they are released to the environment. However, common wastewater treatment plants are
ineffective in removal of dyes from the wastewaters. One of possible options to modify
these facilities to get better outcome is an application of the advanced oxidation processes
(AOPs), i.e., chemical methods based on generation of highly reactive hydroxyl radicals.
In current research, a series of polyaniline-modified TiO2 nanocomposites for photocat-
alytic degradation of dyes, have been successfully synthesized by sol-gel reactions on TiO2
followed by the chemical oxidative polymerization of aniline using ammonium persulfate
(APS) as an oxidant. Fourier-transform infrared spectra (FT-IR), thermal gravimetric analysis
(TGA), X-ray diffraction (XRD), and UV-vis spectra, were carried out to characterize the
composites with different TiO2 contents. The UV-vis spectra confirmed that the optical
absorption for PANI-TiO2 nanocomposite was more intensive than that for pristine PANI
and TiO2 nanoparticles in the visible light region. The intensive visible light absorption
and effective charge separation owing to the heterojunction built between TiO2 and PANI
lead to remarkable improvement of visible light photocatalysis.
The photocatalytic activities of the prepared nanocomposites were evaluated by photocat-
alytic degradation of methyl orange (MO) aqueous solution under visible light irradiation.
The results showed that the surface polyaniline sensitization had no effect on the crystalline
structure but aggravated the agglomeration of TiO2 nanoparticles by formingmulti-particles.
After being sensitized by PANI, the light response of TiO2 was extended to visible-light
regions and the photocatalytic activity of the composite photocatalysts was enhanced. MO
could be degraded more efficiently on PANI-TiO2 than on the bare TiO2 when the weight
percent of TiO2 was 10 wt%. Since γ-irradiation is able to modify the electronic properties
of the photocatalyst, the influence of γ irradiation on the photocatalytic performance was
investigated. A notable enhancement in degradation efficiency and time was found when
irradiated nanocomposites were used. It can be included that γ radiation plays an important
role in the photocatalytic activity of PANI-TiO2 nanocomposites.
IAEA–CN–241–170 375
PA2
PA2-16 Session PA2, Thursday 14:15 Jurkin
Radiolytical Synthesis and Mechanism of Gold Nanoparticle
Formation
T. Jurkin1, M. Gotić1, and G. Dražić2
1Ruđer Bošković Institute, Zagreb, Croatia
2National Institute of Chemistry, Ljubljana, Slovenia
Corresponding Author: T. Jurkin, tjurkin@irb.hr
Gold nanoparticles (AuNPs) are widely used in analytical chemistry, biomedicine and
catalysis. Reducing agent is very important parameter in the synthesis of AuNPs, however,
hypothesis of this study is that AuNPs could be synthesized without using reducing agents,
i.e., that due to very low affinity of gold for oxygen, AuNPs could be synthesized under
highly oxidizing conditions. AuNPs were synthesized in a microemulsion water/TritonX-
100/1-pentanol/cyclohexane using various reducing agents: i) strong chemical reducing
agent (NaBH4), ii) γ-irradiation under moderately strong reducing/oxidizing conditions,
and iii) synthesis under highly oxidizing conditions (with addition of NaOH aqueous solu-
tion). All were performed at room temperature (RT). The size, size distribution, aggregation
and stability of AuNPs in the microemulsions depend on the strength of reducing agent.
When a strong chemical reducing agent NaBH4 was used AuNPs are not well-stabilized
and rather polydisperse. Rather small and monodisperse AuNPs were obtained using
γ-irradiation (30 kGy, 8 kGy/h). γ-irradiation was able to produce AuNPs in air-saturated
microemulsions under highly oxidizing conditions. Smaller AuNPs were obtained by irradi-
ation in the presence of N2 in comparison to the air. The γ-irradiation of nitrogen-saturated
microemulsion at acidic pH produced AuNPs about 10 nm, which aggregated under iso-
lation by centrifugation. The microemulsion stirred at RT and at pHă 7 under oxidizing
conditions did not produce AuNPs, while at pHą 7 (stronger oxidizing conditions) well-
dispersed 12 nm AuNPs were formed. Synthesis of AuNPs in 1-pentanol by adding NaOH
aqueous solution at RT without using microemulsions and irradiation confirmed that oxida-
tion of alcohols was responsible for AuNPs formation. Based on these findings we propose
the base-catalyzed alcohol oxidation at RT as a new, simple and versatile synthesis route for
obtaining gold nanoparticles.
In order to further exploit the oxidation of organic molecules for AuNPs synthesis we
studied the radiolytical synthesis of AuNPs in the presence of citrate. The γ-irradiation of
Au(III)/citrate precursor solutions produced well-dispersed and highly concentrated gold
colloids in the presence of dissolved oxygen, without adding any reducing or stabilizing
agents. AuNP size can be controlled by saturating gases (air or nitrogen) present in the
precursor solution. AuNPs synthesized in the presence of air (10 nm) were approximately
two times larger than AuNPs synthesized in the presence of nitrogen (5 nm), as determined
by UV-vis spectroscopy. An easy radiolytical reduction of Au(III)/citrate precursor solution
in the presence of dissolved oxygen could be explained by enhanced radiolytical oxida-
tion/decarboxylation of citrate to dicarboxyacetone, acetone and other products. Thus,
we confirmed that classical approach of using a reducing agent to synthesize AuNPs is
not a determining factor, since diametrically different approach can be used, namely in
stimulating the oxidation of organic molecules close to gold ions. However, the mechanism
of oxidation of organic molecules during the synthesis is not clear and due to these reasons
we introduced NMR spectroscopy in order to study the oxidation products of alcohol and
citrate ions during the AuNPs synthesis.
376 IAEA–CN–241–210
PA2
Kaci Session PA2, Thursday 14:15 PA2-17
Functional Properties and Ecotoxicity of Bionanocomposites
Based on PHBV/PLA Blend under Electron Beam Irradiation
M. Kaci1
1University of Béjaïa, Béjaïa, Algeria
Corresponding Author: M. Kaci, kacimu@yahoo.fr
Aseptic foodpackagingmaterial is essential to preserve food quality over time. For biodegrad-
able packaging, these materials have to be sterilized or decontaminated prior to use to
protect against possible microbial contamination. Since our knowledge about polyhy-
droxyalcanoates (PHA) for food packaging is rather limited, the challenge is to produce
biodegradable primary packaging materials which remain stable without affecting me-
chanical and barrier properties as well as not resulting in toxicological side-effects during
both storage and usage. Therefore, the present article reports some experimental data
on the oxidative degradation under EB irradiation of neat poly(3-hydroxybutyrate-co-3-
hydroxyvalerate) (PHBV), neat polylactide (PLA) and PHBV/PLA blend (50{50 w/w) with
and without organo-modified montmorillonite, i.e., Cloisite 30B (C30B) (3 wt%) at absorbed
doses of 1 and 10 kGy. The changes in the chemical structure, the molecular weight, the
thermal, mechanical and barrier properties as well as the morphology were evaluated. The
data showed that EB irradiation of PHBV/PLA blend leads to oxidation reactions involving
ester groups in both neat PLA and neat PHBV resulting in the formation of hydroperoxides
groups. The presence of C30B in the polymer blend has no influence on the nature of
the degradation process. However, the good dispersion of C30B nanoparticles provides
more stability to the molar mass and the thermal, mechanical and barrier properties of
PHBV/PLA blend. At absorbed dose of 10 kGy, the irradiated samples are completely safe.
Though there were drastic changes in the chemical structure of the blends, there was no
resulting toxicity as measured using the luminescent bacteria-based bioassay (Microtox).
IAEA–CN–241–036 377
PA2
PA2-18 Session PA2, Thursday 14:15 Khan
Studying the Biological Efficacy of Radiation-Treated
Radiolabelled DOTA-Bombesin-Decorated Nanoconstructs as
Potential Nanosized Drug Delivery Systems
I. U. Khan1, R. Zahoor1, F. Ahmad1, F. Iram2, and A. Shahid2
1Institute of Nuclear Medicine & Oncology (INMOL), New Campus Road, Lahore-54600, Pakistan
2Lahore College for Women University (LCWU), Lahore, Pakistan
Corresponding Author: I. U. Khan, drirfankhan69@gmail.com
The over-expression of neuropeptide receptors in human breast or prostate cancer leads
to potential application of these peptides as agents for cancer diagnosis and therapy. In
this study, we have developed 177Lu-labelled bombesin (BBN) based albumin nanoparticles
(Alb-NPs) and papain nanoparticles (Pap-NPs), thus resulting highly specific radiolabelled
nanoconstructs decorated with DOTA-BBN, and used as emerging novel “nanotheranostics”
for preclinical imaging. The synthesis of gold nanoparticles was developed using green
technology, via stabilization with natural gums (Arabinoxylan-AX isolated from ispaghula
seed husk). As a part of IAEA CRP, the albumin nanoparticles (Alb-NPs) were prepared
in Argentina while papain nanoparticles (Pap-NPs) were prepared in Brazil by ionizing
radiation cross-linking. Particle size of Alb-NPs was tailored by changing the water/ethanol
ratio in the protein solution, reaching particles in the range of 20 nm to 40 nm. The biological
efficacy of DOTA-Bombesin-(Alb-NPs) was tested in Pakistan after labelling with 177Lu.
The quality control was performed by using ITLC-SG strips as stationery phase. There was a
good separation with radiochemical purity (RCP) of 97.3%. The biological efficacy of 177Lu-
DOTA-Bombesin-(Alb-NPs) was tested by determining in vivo uptake through imaging
scintigraphy in normal rabbit models and biodistribution in normal mice. A solution of
177Lu-AlbNPs-DOTA-Bombesin (2 mCi/m`) was injected intravenously into the ear vein
of rabbits (n “ 3). Dynamic study acquisition comprised of 10 frames of 60 s each. It
was followed by anterior and posterior whole body static images acquired at 15 min, 24 h,
48 h, 72 h, and 96 h, post injection. All of these protocols have been established and are
further applied to novel bombesin-derivatized (radiation-treated) nanoconstructs from
other partner labs.
Radiolabelling and quality control was established for 177Lu-Alb-NPs-DOTA-Bombesin.
The effect of activity on labelling efficacy was studied by varying the amount of activity
from 5 mCi to 30 mCi by keeping all parameters constant. Similarly, the effect of volume
over labelling efficacy was studied by varying the amount of volume from 10 to 200 µ`.
The maximum labelling efficacy was found at 10 µ` and beyond 50 µ`, the solution became
turbid. Regarding imaging scintigraphy in normal rabbit models, immediately after the
injection of radiolabelled nanoconstruct, activity was observed to form the blood pool that
was visible in dynamic study of 15 min. In static images, it was further observed that
the compound showed a slower uptake with a significantly higher retention time in liver
and spleen, thus leading to sufficient renal excretion to allow absorption of the labelled
compound into tumor, with rapid body clearance.
In summary, this approach might be further extended to tumor-specific targeting by using
BBN derivatives as carrier of chemotherapeutic agents. Imaging studies performed with
177Lu-Alb-NPs-DOTA-Bombesin demonstrate its ideal therapeutic potential to be further
developed as a feasible theranostic agent, during this CRP.
378 IAEA–CN–241–352
PA2
Kim Session PA2, Thursday 14:15 PA2-19
Fabrication of Advanced Soft Magnetic Nanomaterials Using the
Radiation
H. B. Kim1, J.-M. Yun1, S.-H. Oh1, and S. Yu1
1Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
Corresponding Author: H. B. Kim, hbkim@kaeri.re.kr
Soft magnetic materials have been investigated for applications in magnetic devices such as
transformers, inductor, electromagnetic (EM) wave shielding, etc. Its magnetic properties
are determined by composition, crystal structures and size. Many kinds of research are
focussed on the control of material size chemically and mechanically. Synthesis of particles
using an electron beam (EB) irradiation provides stable and high quality. In this study,
we synthesized the iron oxide particles using a 10 MeV EB irradiation. This material has
fine nanosphere with Fe3O4 phase in the result analysis of FE-SEM and XRD. And it also
possible to fabricate the α-Fe2O3 phase with different precursor compositions. As increasing
the EB irradiation dose, the saturation magnetization of particles dramatically increased
up to 300 kGy. This result is related to the growth of crystal phase. To evaluate the uses of
this material in high frequency, the complex permittivity and permeability of composite
were measured by network analyzer from 300 kHz to 8.5 GHz in forms of composite in
wax matrix. This material shows the high return loss (over than ´40 dB) near 6 GHz.
These results clearly demonstrate that the radiation is a good candidate for the nanoparticle
fabrication and industrial applications.
IAEA–CN–241–237 Presenter: S. Yu 379
PA2
PA2-20 Session PA2, Thursday 14:15 Klingbeil
Development of Advanced Scaffolds and Polymeric Systems for
Improved Cell and Tissue Growth
M. Klingbeil1, J. Ernesto2, P. Lopes2, D. Rocha1, J. Oliveira1, G. H. C. Varca1, C. Silva2,
D. Steffens3, A. B. Lugão1, and M. Mathor1
1Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), São Paulo, Brazil
2Universidade Federal de São Paulo, São Paulo, Brazil
3Federal University of Rio Grande do Sul, Porto Alegre, Brazil
Corresponding Author: M. Klingbeil, fakling@usp.br
The recent concern related to skin compromised patients, apart from the nature of the
condition itself, such as wounds, chronic ulcers, or burns among others, has triggered
and highlighted the importance of the development of artificial skins available in allo-
geneic donor tissue banks and/or scaffolds, composed by a wide variety of biocompatible,
biodegradable and bioactive biomaterials. Within this context, tissue engineering has been
in expansion as an attempt to overcome difficulties faced in such situations. The application
of scaffolds, produced or not by nanotechnology, in the skin of a patient induces cells to
proliferate and get organized on extracellular matrix regenerating tissue. Ionizing radiation
is a particularly useful technology capable of promoting sterilization and cross-linking of
the scaffold structure thus offering several possibilities for the development of advanced
systems suitable for cell growth. Taking into account the variety of clinical applications of
tissue engineering, the aim of this study was to investigate by means of histological tests,
chemistries and non-destructive tests, the interaction of mesenchymal stem cells grown
in vitro in conjunction with different frameworks in order to understand how the mesenchy-
mal stem cells behave in different niches. Among those collagen, PVA, chitosan, PDLLA
scaffolds were the systems of choice and γ-irradiation was applied for sterilization of the
systems, as well as cross-linking for the PVA based scaffold. Thus this work allowed the
achievement of dermo-epidermic matrices populated by epidermal cells that make up the
skin and will contribute to the development of a more robust and useful material to be used
in several treatments.
380 Presenter: G. H. C. Varca IAEA–CN–241–412
PA2
Krstić Session PA2, Thursday 14:15 PA2-21
Mechanical Characteristics and Antibacterial Properties of
Ag-Poly(Vinyl Alcohol)/ws-Chitosan Hydrogel Nanocomposites
Synthesized by γ-Irradiation Combined with Freeze/Thaw
Cycles
J. Krstić1, A. Radosavljević1, J. Spasojević1, D. Jovanović2, S. Popović3, and
Z. Kačarević-Popović1
1Vinča Nuclear Institute, University of Belgrade, Belgrade, Serbia
2Institute of Microbiology, Military Medical Academy, Belgrade, Serbia
3Clinic for Endocrinology, Diabetes, and Metabolic Diseases,
Faculty of Medicine, University of Belgrade, Belgrade, Serbia
Corresponding Author: J. Krstić, jelenak@vinca.rs
Hydrogels have been used successfully in many biomedical applications including scaffolds
for wound healing applications or soft tissue implants. A problem for the biomedical ap-
plication of hydrogels is that microorganisms may grow in hydrogels due to their natural
biocompatible properties. Improvement in application of hydrogels is often achieved by
the addition of natural polysaccharide or non-specific antimicrobial species such as Ag
nanoparticles. The antibacterial bio-synthetic hydrogel nanocomposites consist of blends be-
tweenwater soluble derivatives of radiation processed chitosan (ws-chitosan) and poly(vinyl
alcohol) cross-linked by γ-irradiation (via 60Co source) and radiation in situ incorporated
Ag nanoparticles (AgNPs). Chitosan is a copolymer composed of glucosamine and N-
acetyglucosamine sugars, linked by 1–4 glucosidic bonds, both of which are constituents of
mammalian tissues. Chitosan degradation by ionizing radiation gives structural diversity
which contributes to its wide application in biomedicine. The radiation technology platform
allows synthesis by environmentally friendly and biocompatible radiolytic products of water.
The postirradiation hydrogel freeze-thaw procedure was performed to enhance mechanical
properties and to prevent liking of un-grafted ws-chitosan during AgNPs synthesis. The
thus obtained ws-chitosan, poly(vinyl alcohol)/ws-chitosan polymer matrix and nanocom-
posites were subjected to molecular weight determination (by Zetasizer), FT-IR, NMR, SEM,
elemental analysis and mechanical characterization by thermomechanical analysis, in static
stress/strain and dynamic mode. The antibacterial properties against Escherichia coli and
Staphylococcus aureuswere assessed by using the agar diffusion test. Results revealed the
partial formation of Maillard reaction products during radiation degradation of chitosan.
The non-linear stress-strain data from unconfined compression test were fit by the Kennedy
equation and by an elastic model (Rige andWright). The results indicated changes in matrix
mechanical resistance upon incorporation of ws-chitosan. In contrast, AgNP incorpora-
tion decreased the polymer matrix elasticity while increasing the cross-linking density of
polymer network and provides more rigidity to the structure which increases the values
of storage modules (obtained in dynamic mode) and, as a consequence, causes a better
mechanical stiffness of the network. The antibacterial activity of Ag-poly(vinyl alcohol)/ws-
chitosan hydrogels show enhanced antibacterial potential in comparing with poly(vinyl
alcohol)/ws-chitosan hydrogel matrix only. For investigated hybrid hydrogel, zone of in-
hibition is greater against Staphylococcus aureus than for Escherichia coli. This is important
for the treatment of wound infections in diabetic patients which are dominantly caused by
aerobic Gram-positive cocci. These promising results give possibility for development and
optimization of synthesized antibacterial Ag-hydrogel nanosystems.
IAEA–CN–241–261 381
PA2
PA2-22 Session PA2, Thursday 14:15 Li
Dyestuff Free: Colouring Fabrics by Graft Polymerization
J. Li1, M. Yu1, Z. Wang1, and B. Zhang1
1Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai Shi, People’s Republic of China
Corresponding Author: J. Li, jingyeli@sinap.ac.cn
Laundering durable functional fabrics are obtained by means of radiation-induced graft
polymerization methods, via the graft polymerization of functional monomers or co-graft
polymerization of the monomers and certain nanoparticles r1–4s. The laundering durability
lies in the formation of the covalent bonds between the cellulous macromolecules and the
graft chains or together with the nanoparticles, which is the most advantage of the radiation
methods in fabric modification.
Dyestuffs, normally referring to the organic molecules which can be dissolved or dispersed
in solutions, are used to colour cotton fabrics since they can be absorbed by the nanoporous
structure and the non-crystalline zone, or even the lamella of the crystalline zone of the fab-
rics. Reactive dyestuffs can react with the hydroxyl groups on the cellulous macromolecules
under high temperature and basic conditions. Although dyestuffs are well-developed
chemical products and the dying process is mature too, the long treating period and high
pollution of the waste water needs to be solved.
In our previous study, we found that radiation-induced graft polymerization methods will
be a dyestuff-free way to colour the cotton fabrics by co-graft polymerization the colourful
nanoparticles. For example r5s, MIL-101, a typical metal organic framework (MOF) which
comprises a nontoxic chromium(III) cluster and benzene-1,4-dicarboxylate ligand, was
co-graft polymerized onto nylon fabric with 2-hydroxyethyl acrylate (HEA), owing to the
abundance of benzene rings in MIL-101 which favours free radicals generation on its surface.
The colour of MIL-101 is dark green, and the colour of the grafted nylon fabrics is green and
darkens with the increasing degree of grafting of MIL-101. More important, the robustness
of the product was demonstrated by 30 hours dry-cleaning test using tetrachloroethylene as
the organic solvent, and most of the MIL-101 particles still adhered to the nylon fabric after
the washing.
Base on the above facts, we are now developing the dyestuff-free colouring fabric procedure
by fixing pigments micro- or nanoparticles onto the cotton fabric under radiation-induced
co-graft polymerization methods.
References
r1s B. Deng, et al., Adv. Mater., 22, 5473–5477 (2010).
r2s J. X. Wu, et al., Sci. Rep., 3, 2951 (2013).
r3s B. T. Wu, et al., Sci. Rep., 5, 11255 (2015).
r4sM. Yu, et al., ACS Appl. Mater. Interfaces, 5, 3697–3703 (2013).
r5sM. Yu, et al., Sci. Rep., 6, 22796 (2016).
382 IAEA–CN–241–058
PA2
Lucan Session PA2, Thursday 14:15 PA2-23
Influence of the Coolant Chemistry on the Structural Materials
Surfaces Exposed into the Candu NPP Primary Circuit
D. Lucan1
1Institute for Nuclear Research Pitesti (RATEN–ICN), Mioveni, Arges, Romania
Corresponding Author: D. Lucan, dumitra.lucan@nuclear.ro
One of the most important NPP plant systems is the primary heat transport system (PHTS)
having in view its role in active zone cooling and heat transfer to steam generators. In PHTS,
chemical control is directed to keep chemical parameters within specified limits in order to
mitigate the corrosion of the key equipment and related piping, to control the corrosion rate
and impurities concentration, such as corrosion andfission products and tominimize activity
transport and heat transfer surfaces fouling. By operation in aqueous environment at high
temperature and pressure, the structural materials from PHTS cover with protective oxide
films, which maintain the corrosion rate in admissible limits. Many potential factors exist,
which conduct to degradation of the protective films and consequently to intensification of
the corrosion processes. The existing experience of different nuclear reactors shows that the
water chemistry has an important role in maintaining the integrity of the protective oxide
films. In order to minimize the adverse effects, an optimal water chemistry control and
corrosion monitoring programme were established. The understanding of the corrosion
degradation phenomena that conduct to failure of some components from PHTS of CANDU
NPP implicates the investigation of the structural materials corrosion processes, in different
conditions of water chemistry and temperature. To investigate the corrosion process of some
structural materials from PHTS (Zr and Ni alloys) of CANDU 6 reactor were performed the
following activities:
• out of pile corrosion experiments in different conditions of water chemistry;
• corrosion experiments in autoclaves assembled in by-pass of CANDU 6 reactor PHTS;
• corrosion analysis performed on some corroded components.
The gravimetric method, optical metallographic microscopy, XRD analysis, as well as electro-
chemical measurements have been used to evaluate the corrosion behaviour of the pressure
tube and steam generator tubing materials. The obtained results allowed us to establish
the contribution of the water chemistry in the initiation and evolution of some accelerated
corrosion processes.
IAEA–CN–241–294 383
PA2
PA2-24 Session PA2, Thursday 14:15 Lungulescu
Radiation-Induced Oxidation in γ-Irradiated UHMWPE
Modified with Hydroxyapatite
E.-M. Lungulescu1, T. Zaharescu1, R. Setnescu1, A.-M. Luchian1, and M. Rapa2
1National Institute of Research and Development for Electrical Engineering (ICPE-CA), Bucharest, Romania
2Institutul de Cercetari Produse Auxiliare Organice (ICPAO-Medias), Medias, , Romania
Corresponding Author: E.-M. Lungulescu, marius.lungulescu@icpe-ca.ro
The medical use of ultra-high molecular weight polyethylene (UHMWPE) as bone replace-
ment as well as the manufacture of sterile sealed cases and envelopes require detailed
investigations on the chemical stability over long time wear. To impart high similarity to
substituted hard parts of osseous system, the addition of hydroxyapatite to the polymeric
material is an attractive option. The present study investigates three polymer composites
consisting of UHMWPE and LDPE to which hydroxyapatite (HAP) was added in the con-
centration of 10%. Some of samples were stabilized with rosemary extract powder (0.5%).
Films and flat plates were obtained by melting in a BRABENDER Plastograph, under a
mixing temperature of 180˝C for 10 min and screws rotation rate of 40 rpm followed by the
thermal processing in a laboratory press type POLYSTAT 200 at the following conditions:
temperature: 165˝C, pressing time 3–6 min, pressure of 125–150 atm and cooling time of
30 min. Accelerated degradation by γ-exposure was carried-out in air inside of the Ob Servo
Sanguis (Hungary) 60Co irradiator, whose dose rate was 1.1 kGy/h. The stability and
structural characterization were done by isothermal (180˝C) and nonisothermal (heating
rate: 10˝C/min) differential scanning calorimetry in inert and air environments and by
ATR-FTIR spectroscopy. The influence of hydroxyapatite and rosemary powder is noticed
by the improvement in the kinetic parameters: the decrease of oxidation rates and the
extension of total oxidation periods. The progress in the ageing degree is described by
the carbonyl index, whose variation is connected to the inhibition promoted by the large
surface of hydroxyapatite particles playing the role of adsorbent of free radicals and by the
scavenging activity of rosemary components, where the predominant active principle is
carnosic acid. In spite of the difference in the behaviour of polymeric components relative
to the oxidative degradation the evolution of oxidation looks similarly in respect to the accu-
mulation of initiators, hydroperoxyl radicals. The oxidation resistance of studied blends is
ameliorated because the both polymeric components are regarded as sources of free radicals,
but the addition of hydroxyapatite and rosemary powder makes possible the manufacture
of products with long term applications. The contribution of HAP and rosemary additive is
significant not only on the early stages of ageing, but also during the exposure to a severe
energetic transfer.
The efficiency in the oxidation delay in UHMWPE/LDPE blends can be expected when the
stress agents are less strong than γ-radiation. However, the comparative study involving
indoor weathering degradation is foreseen, because the oxidation strength of these compo-
sitions including hydroxyapatite allows the extension of usage ranges in several areas as
outdoor components of industrial devices.
384 IAEA–CN–241–188
PA2
Madrid Session PA2, Thursday 14:15 PA2-25
Optimization of Electron Beam-Induced Synthesis of
Polypropylene-g-poly(Glycidyl Methacrylate) for Cr(VI) and
Cd(II) Adsorption Using Full Factorial Design
J. Madrid1, L. V. Abad1, and G. E. Lopez1
1Philippine Nuclear Research Institute (PNRI), Quezon City, 1107 Metro Manila, Philippines
Corresponding Author: J. Madrid, jfmadrid@pnri.dost.gov.ph
Graft copolymerization is an efficient and attractive method to impart a variety of functional
groups to commercially available polymers. This method allows the development of new
materials that cannot be synthesized using conventional processes. In this work, carboxylic
acid- and amine-type adsorbents were developed from polypropylene nonwoven fabric (PP
NWF) using the emulsion phase radiation-induced graft polymerization (RIGP) technique.
The set of optimum parameters (e.g., absorbed dose, reaction time, monomer concentration)
for grafting glycidyl methacrylate (GMA) on PP trunk polymer was determined using
full factorial design. Post-grafting reactions of the poly(glycidyl methacrylate) (PGMA)
grafted on PP NWF with ethylenediamine (EDA) and iminodiacetic acid (IDA) imparted
approximately 3.0 and 1.2 mmol functional groups per gram-adsorbent, respectively. These
covalently bonded chemical groups serve as active sites in the removal of Cr(VI) and Pb(II)
from aqueous solutions. Preliminary data suggest that the EDA and IDA functionalized PP
has high affinity for Cr(VI) and Cd(II) ions, respectively.
IAEA–CN–241–189 385
PA2
PA2-26 Session PA2, Thursday 14:15 Mahmoud
Radiation Development of (Polyvinyl Pyrrolidon/Acrylic Acid)-
Silver Nanocomposite for the Disposal of Phenolic Compounds
from their Aqueous Solutions
G. Mahmoud1, T. Mostafa2, and A. Raafat1
1Egyptian Atomic Energy Authority (EAEA), Cairo, Egypt
2Ain Shams University, Cairo, Egypt
Corresponding Author: G. Mahmoud, ghadancrrt@yahoo.com
Nitroaromatic compounds are considered to be amongst the most prevalent organic pollu-
tants in wastewater. They are intermediates or side products of many industrial products
such as dyes, pharmaceuticals, agrochemicals, cosmetics, photographic chemicals, addi-
tives, chelating agents, and other products. 4-nitrophenol (4-NP) is a notorious industrial
pollutant exhibiting a high solubility and stability in wastewater. The direct exposure to
these pollutants causes inflammation of eyes, skin and respiratory tract and prolonged
contact with skin may cause an allergic response. Much effort has been expended to de-
velop methods for removing the aromatic pollutants from wastewater. The reduction of
nitroaromatic compounds to the benefit amines is considered to be the most efficient, green,
and economical approach to disposing of the nitro-compounds. The reduction product,
4-aminophenol (4-AP), can be reused because it is important intermediate for the synthesis
of drugs and dyes. Therefore, various nanoparticles have been employed as an effective
catalyst for the reduction of nitroaromatic compounds in aqueous solutions under mild
conditions. The main issue hinders the pervasive use of homogeneous metal nanoparticles
as a catalyst is their high tendency to aggregate as a result of the size and high surface energy
of metal nanoparticles. Moreover, the problems in separating the products contaminated
with unstable residuals and recycling the expensive catalysts. To prevent aggregation of
metal nanoparticles, diverse supportive materials such as hydrogels are widely employed.
Hydrogels are hydrophilic polymeric three-dimensional networks capable of absorbing
a large amount of water. The catalytic reactions can take place within the boundaries of
hydrogels, no need to change many reactor conditions in industrial applications; just a right
choice of hydrogel-composites can supply all the necessary conditions.
In this study, poly vinyl pyrrolidone/acrylic acid (PVP/AAc) hydrogels were prepared via γ-
irradiation technique. (PVP/AAc) hydrogel was utilized as a supportingmaterial to stabilize
Ag nanoparticles by employing in situ method to obtain (PVP/AAc)/Ag nanocomposite.
The catalytic activity of (PVP/AAc)/Ag nanocomposite was investigated in the reduction
of (4-NP) in sodium borohydride solution (NaBH4). Parameters that affect the reduction
rate were investigated. It was found that the reaction proceeded with the conversion
exceeding 99.8% at a reaction time of about 5min for (PVP/AAc)/Ag nanocomposite loaded
with 231.76 mmol/` Ag. The rate of the reduction reaction decreased with increasing
the concentration of 4-NP and the optimum concentration of NaBH4 was found to be
0.164 mol/`.
386 IAEA–CN–241–126
PA2
Mahmoud Session PA2, Thursday 14:15 PA2-27
A Comparative Study of Radiation Sterilization of Cell Culture
Media and Filtration Sterilization Method in Cell Culture
Laboratory
A. Mahmoud1, A. Salih1, M. Alkhansa1, W. Almahi1, N. Elteib1, and A. Yousif1
1Sudan Atomic Energy Commission, Khartoum, Sudan
Corresponding Author: A. Mahmoud, alkhansa.salih@gmail.com
Cell culture media is uses in biopharmaceutical processes to stimulate the natural environ-
ment of the cell. Media used in cell culture have a balanced salt solution; the most commonly
used is sodium bicarbonate with a pH of 7.2–7.4 at 37˝C that the optimal growth of cells.
Filtration is a safe method used for media sterilization in cell culture laboratory; it helps to
removes the microorganisms, but is unable to separate microorganisms that have the same
size. The most common types used in tissue culture has a pore size 0.2 µm. The aim of this
study is using γ-radiation to sterilize media in cell culture laboratory compared to filtration
sterilization method.
For media preparation, RPMI-1640 media in powder form, containing vitamins, minerals,
amino acids and red phenol, was added to NaHCO3 and dissolved in distilled water, and a
pHmeter was used for pH determination. A 60Co γ-irradiator was used for dose irradiation
of 5 kGy and 20 kGy at 1.26 kGy/h dose rate. The irradiation was carried out at the
Chemistry and Physics Institute of the Sudan Atomic Energy Commission.
Testing of bacteria included total viable aerobic count and total coliform count. Cell viability
testing was made by adding 0.5 m` of lymphocytes to 4.5 m` from RPMI media, 1.2%
penicillin/streptomycin, 1% fetal bovine serum, 30 µm` Phytohaemagglutinin glutamine,
and then incubated for 24 hours in CO2 incubator. Cells were then counted using jumper.
A γ-radiation dose of about 20 kGy was found to be enough to destroy most type of bacteria
rather than 5.0 kGy, but not suitable for sterile media cell culture in laboratory because
increasing the probability of poor cell growth. While a dose of 5 kGy does not completely
sterilize the media and cell growth observed. Physiology of media environment is summa-
rized as follows for Lymphocytes growth and pH control for γ radiation dose and filtration
for sample media:
Media Cell Death Cell Growth pH (pre) pH (post) Media
Sterilization (24 Hours) (48 hours) Colour
5 kGy 50% 50% 7.2 7.2 change
20 kGy 70% 10% 7.2 8.0 colourless
Filtration 10% ą 60% 7.2 7.3 no change
Media can be sterilized by γ-radiation with doses larger than 5 kGy, but red phenol that
indicator pH of media was degraded with increases the γ-dose. This result suggests that
γ-doses larger than 5 kGy and less than 20 kGy should be tested to achieve the dose range
accepted for cell culture media sterilization without affecting cell integrity. Then, radiation
sterilization amongRPMImediamay useful for liquid RPMImediawithout red phenol, used
in stem cell. Further research on red phenol degradation by γ-radiation, and amino acids
concentrations post-γ irradiation is strongly recommended, and might help in sterilization
and modifications of media for various cell culture applications using γ-rays.
IAEA–CN–241–401 387
PA2
PA2-28 Session PA2, Thursday 14:15 Mandal
Simultaneous Radiation Grafting of Acrylic Acid on
Polypropylene Films: Optimization, Biodegradability and
Evaluation of Ecotoxicological Impact
D. Mandal1, P. K. Bajpai1, H. Bhunia1, C. Chaudhari2, A. Dubey2, and L. Varshney2
1Department of Chemical Engineering, Thapar University, Patiala 147004, Punjab, India
2Radiation Technology Development Division, Bhabha Atomic Research Centre (BARC), Mumbai, India
Corresponding Author: D. Mandal, devkumar@thapar.edu
Polypropylene (PP) is used as a packaging material because of low cost and water resistance
properties. However, it has been much criticized for its lack of degradability. Simultaneous
radiation grafting is a versatile method by which acrylic acid (AAc) has been grafted on
the surface of PP. From our previous work, it was found that the biodegradability of AAc
grafted PP did not significantly improve beyond 34% degree of grafting. Now, there is a
need to optimize the grafting condition for „ 35% degree of grafting, and study the effects
of process parameters on it. It is also important to know the ecotoxicological impact of
biodegradation product of grafted PP films.
Simultaneous radiation grafting was done with 60Co γ-radiation. Experiments were de-
signed based on response surface methodology (RSM) to optimize the monomer concen-
tration (6.88–13.52 wt%), radiation dose (6.74–13.42 kGy), inhibitor concentration (0.01–
0.11 M) and solvent concentration (0.12–0.36 M) for the 35% degree of grafting. The grafted
PP films were characterized by tensile test, fourier transform infrared spectroscopy (FTIR),
differential scanning calorimetry (DSC) and biodegradability. Ecotoxicological impact was
evaluated by microbial test and plant growth (corn and tomato) test as per the OECD test
#208 guidelines.
The number of experiments reduced to 30 only for the optimization of grafting conditions for
the 35% degree of grafting. The suggested optimized conditions for 35% degree of grafting
were monomer concentration 12.09 wt%, radiation dose 12.40 kGy, inhibitor concentration
0.07 M and solvent concentration 0.12 M, it was also experimentally verified in triplicate
and average degree of grafting achieved was 34%, which is almost same as suggested 35%
by the RSM. Grafting of AAc onto PP films was confirmed by FTIR. Tensile strength of
PP18 (35% grafted) was 21.1 MPa which is suitable for packaging applications (as against
38.8 MPa of PP). The crystallinity of PP18 (26%) was lower than PP (59%) shown by DSC.
The biodegradation achieved was 5.5% at 35% degree of grafting by following the guideline
of American Society for Testing and Materials (ASTM D 5338-11). Ecotoxicological test
indicated that biodegradation products were non-toxic in nature.
Grafting conditions were optimized by RSM for 35% degree of grafting and experimentally
verified. Biodegradation 5.5% was achieved with 35% grafted PP film. Eco-toxicological
test confirmed that no degradation product of grafted PP has any environmental toxicity.
388 Presenter: H. Bhunia IAEA–CN–241–047
PA2
Marušić Session PA2, Thursday 14:15 PA2-29
Metal Surface Modification with Fatty Acids Using Ionizing
Radiation
K. Marušić1, H. Otmačić Ćurković2, I. Tartaro Bujak1, and B. Mihaljević1
1Ruđer Bošković Institute, Zagreb, Croatia
2Faculty of Chemical Engineering and Technology, University of Zagreb, Zagreb, Croatia
Corresponding Author: K. Marušić, kejt.marusic@gmail.com
Various metals and alloys are commonly used in medicine. As such they are often exposed
to aggressive environments and thus subjected to corrosion, i.e., dissolution. Thus, modifi-
cation of the metal surface is interesting since the resistance to corrosion can be increased
and the durability of the object can be prolonged.
Medical equipment, in most cases, must be sterilized and a common method uses ionizing
radiation. While ionizing radiation does not markedly influence the properties of the metal
it can influence the protective layer that is formed on its surface.
Fatty acids are non-toxic compounds which have an affinity for self-assembling on metals
and therefore lately they have been investigated as possible protective layers on metals.
The influence of ionizing radiation on the formation of such layers is needed to determine
whether it changes the properties of the protective layer or maybe even enhances them.
Procedures for adsorption of self-assembling layers of fatty acids onmetals exist in literature.
This work studies influence of ionizing γ-radiation on the process of assembling such a
layer and the efficiency of the outcoming layers in corrosion protection.
Various variables are studied. The most important variables are the applied γ-irradiation
dose, as well as the dose rate at which it is applied. The quality and efficiency of the obtained
layers in corrosion protection are studied by electrochemical methods.
The results have shown that the layer of fatty acid that forms on the surface of themetal using
ionizing radiation offers additional protection to the bare metal making it more resistive
to corrosion. For successful formation of a protective layer on the metal it is essential to
determine the proper molecule which has good adhesive properties and to irradiate with
an appropriate dose, at an optimal dose rate.
IAEA–CN–241–235 389
PA2
PA2-30 Session PA2, Thursday 14:15 Marzouki
Irradiation Effects on Structure and Spectroscopic Properties of
Sugar Doped Sol-Gel Silica
K. Marzouki1, H. Ben Ouada2
1National Center for Nuclear Sciences and Technologies (CNSTN), Sidi Thabet, Tunisia
2Faculté des Sciences, Université de Monastir, Monastir, Tunisia
Corresponding Author: K. Marzouki, kaouther.marzouki@cnstn.rnrt.tn
Silica xerogel doped sucrose was prepared via sol-gel process and exposed at room tem-
perature to different doses of 60Co γ-irradiation. Changes in the physical properties of
the xerogels before and after irradiation were characterized by using UV-visible and FTIR
spectra of pristine and irradiated xerogels with varying of γ-ray dose, showing a variation
in the gap energy. It was found that the γ-irradiation influences the optical properties and
modifies the network structure. Then, results indicate that the gap energy of the inves-
tigated silica xerogels decreases with increasing γ-dose. Thereby the irradiated samples
reveal behaviour changes, from an insulator (Eg „ 5.8 eV) towards a semiconductor with
(Eg „ 3.5 eV).
390 IAEA–CN–241–332
PA2
Mohd Janib Session PA2, Thursday 14:15 PA2-31
Ionizing Radiation Engineered Functional Nanogels for
Biomedical Applications
S. Mohd Janib1, M. Y. Hamzah2, R. Tajau2, W. H. B. Wan Kamal1, S. S. Abdul Hamid1,
M. F. Ahmad Fadzil1, and Y. Ng1
1Medical Technology Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang, Selangor, Malaysia
2Radiation Processing Technology Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang, Selangor,
Malaysia
Corresponding Author: S. Mohd Janib, najila@nuclearmalaysia.gov.my
Nanoscale therapeutic systems have emerged as novel therapeutic modalities for cancer
treatment and are expected to lead to major advances in cancer detection, diagnosis and
treatment. At Nuclear Malaysia, we have developed a nanoplatform that would be suitable
to use for the targeted delivery of imaging and therapeutic agents.
Nanogels are nanoparticles consisting of internally cross-linked hydrophilic polymers of
sub-micrometer size. The polymeric nanogels used in this study were synthesized via
irradiation of polyethylene glycol-diacrylate (PEG-DA) using electron beam. Radiation
induced synthesis of nanogels not only ensures polymer cross-linking, but also particle size
control, chemical functionalization and sterilization of the product material. In addition it
has the advantage of ease of scale up and the absence of potentially toxic monomers and
cross-linking agents. With superior colloidal stability, inertness in the bloodstream and high
drug loading capacity, nanogels make an ideal nanocarrier for biomedical applications.
The prepared nanogels were characterized by scanning electron microscopy (SEM). Their
size and zeta potential were measured using dynamic light scattering and zeta potential
analyzer respectively. Biocompatibility of the nanoparticles were assessed by MTT assay.
To assess the applicability of the nanogels as a drug carrier, a tumor targeting peptide is
appended to the nanoparticle to endow it with tumor homing/targeting capability. Addi-
tionally, to track its biodistribution in vivo, it was radiolabelled with a suitable positron
emission tomography (PET) radioisotope and scanned using a PET camera to assess its
tumor targeting capability and accumulation.
IAEA–CN–241–344 391
PA2
PA2-32 Session PA2, Thursday 14:15 Mollah
Effect of γ-Radiation on the Physico-Mechanical Properties of
Gelatin-Based Films and Jute-Reinforced Polymer Composites
M. Z. I. Mollah1, R. A. Khan1
1Bangladesh Atomic Energy Commission (BAEC), Dhaka, Bangladesh
Corresponding Author: M. Z. I. Mollah, zahirul1973@yahoo.com
Gelatin, a natural protein, is insoluble in water and is solubilized by hydrolysis. Gelatin
based polymeric films were prepared in aqueous medium by casting. The mechanical
properties were evaluated by proper method. The tensile strength was found to be 27 MPa.
Gelatin films were soaked in different formulations containing 2-hydroxyethylmethacrylate
(HEMA), methanol and photo-initiator and then irradiated under γ-radiation. Again, a
series of gelatin solutions was prepared by blending varying percentages (10–50 wt%) of
HEMA and then films were prepared and irradiated under γ-radiation. It was found that
tensile properties of gelatin films improved significantly. In another investigation, jute
fibre reinforced polypropylene (PP) composites were prepared by compression molding.
Composites were fabricated with varying percentages of jute and irradiation dose. Total
radiation dose varied from 250–1000 krad and composites made of using 500 krad showed
the best results.
392 IAEA–CN–241–001
PA2
Negrin Session PA2, Thursday 14:15 PA2-33
Ionizing Radiation as a Tool to Affect Polymer Biodegradation
M. Negrin1, E. Macerata1, M. Giola1, M. Soccio1, N. Lotti1, and M. Mariani1
1Politecnico di Milano, 20133 Milano, Italy
Corresponding Author: M. Negrin, maddalena.negrin@polimi.it
The great stability and durability of conventional synthetic plastics and their outstanding
properties have allowed a wide range of potential applications among which packaging
constitutes the larger market segment. However, due to the specific function, packaging
rapidly becomes waste that increasingly accumulates in the environment. Therefore, nowa-
days the need of biodegradable polymers is growing and great efforts have been devoted to
optimize the use and the disposal of conventional non-biodegradable plastics favouring their
degradation in the environment. Aliphatic polyesters have attracted considerable attention
combining biodegradability and biocompatibility features with physical-chemical proper-
ties comparable with some of the most extensively used polymers. It is well known that
ionizing radiation can modify polymers and enhance or degrade their properties, affording
many practical applications. In particular, γ-radiation can facilitate material degradation by
inducing oxidative fragmentations of polymer backbone. In this viewpoint, experimental ac-
tivities have been addressed to investigate if a radiation treatment of bio-based plastics in an
ambient promoting or accelerating degradation, could represent an effective pretreatment
for improving their biodegradation.
Commercial and synthesized polymers, such as polyethylene (PE) and polybutylene succi-
nate (PBS), have been irradiated by 60Co sources and the impact on the rate of biodegradation
in compost has been evaluated. Polyesters, in films up to 200 µm, have been irradiated
at absorbed doses up to hundreds of kGy in air and aqueous solution, and examined by
different techniques. Radiation-induced changes of the chemical properties have been
evaluated as a function of the absorbed dose and the effect of the oxidative ambient has been
compared with that of irradiation in air. The molecular weight data obtained by gel perme-
ation chromatography indicate that biodegradable polymers show a more significant loss
of molecular weight with respect to PE as the dose increases. On the contrary, the thermal
behaviour investigated by differential scanning calorimetry does not seem to be affected by
the treatment at these absorbed doses. In addition, the surface properties have been carefully
evaluated in order to correlate their changes to the biodegradability in compost. In the case
of PBS systems water contact angle measurements show that the hydrophilicity is affected
already at the lowest absorbed doses, coherently with the remarkable decrease of molecular
weight. The research performed confirmed that the radiation-induced degradation could
be considered as an effective pretreatment able to enhance the biodegradation rate of some
polymeric systems.
IAEA–CN–241–238 393
PA2
PA2-34 Session PA2, Thursday 14:15 Nik Salleh
Development of Nanocomposite Coatings by Radiation Curing
N. G. Nik Salleh1, M. S. Alias1
1Malaysian Nuclear Agency, Bangi, 43000 Kajang, Selangor, Malaysia
Corresponding Author: N. G. Nik Salleh, nik_ghazali@nuclearmalaysia.gov.my
Kencana Fibrecomposite is a manufacturer producing high performance fibre composite
derived from a revolutionary green technology. These composites are alternatives to wood
and used in building construction. At present, these materials are ready to be used without
coating or painting, however they are vulnerable to scratch and abrasion during handling
and transportation. Therefore, Kencana Fibrecomposite and Nuclear Malaysia have col-
laborated to develop scratch and abrasion resistant nanocomposite coating materials. The
most appropriate process to cure the materials is using radiation curing technology. The
technology offers several advantages such as fast curing, improved productivity and product
performance, curing at room temperature and elimination of volatile organic compound
(VOC).
In this research work, the incorporation of silica nanoparticles into radiation curable resins
is to enhance scratch and abrasion properties of the coating materials while retaining
transparency and glossiness. Radiation curable nanomaterials can be prepared using het-
erogeneous hydrolytic condensation technique. Composite materials that exhibit a change
in structure and composition over nanometer length scale have been proven in imparting
remarkable property enhancement with respect to stiffness and strength. The technique
is also capable of overcoming several major issues related to compatibility between the
matrix and the nanoscale component, and also agglomeration of nanosized component
during processing. This will produce a homogeneous distribution of nanosilica in the
radiation curable nanomaterials. Silico-organic nanoparticles have relatively large surface
areas compared to microparticles, therefore modification effects from the polymerization
activity should have a great influence on the properties of the composites.
During curing process, electron beam (EB) radiation and ultraviolet (UV) light were used to
initiate radical polymerization. These polymerization active nanoparticles were obtained
from heterogeneous hydrolytic condensation of the silane to the silanol groups of the silica
particles. The above reaction could be verified by the application of FT-Raman spectroscopy
(intensity measurement of the C--C vibration band at 1640 cm´1) and gel permeation chro-
matography to show the impact of polymerization activity of the nanoparticles on the
silico/acrylate dispersion. In the curing process, the nanoparticles form cross-linkages to
produce radiation cured polymeric composite with improved scratch and abrasion resis-
tance. From Taber abrasion, it can be observed that the weight losses of radiation cured
materials are significantly reduced when the amount of silica particles (SiO2) increases. The
nanoparticles added into the coating materials significantly improved the scratch property.
Finally, it can be concluded that polymerization active silico-organic nanoparticles could
be prepared by in situ reaction. Formulations useful for technical coating process could be
prepared and cured using the low energy electron beam (EB) and ultraviolet (UV) light.
The composite materials showed highly improved mechanical properties. These polymeric
nanocomposites show excellent resistances toward abrasion and scratch properties when
compared to pure materials without nanoparticles.
394 IAEA–CN–241–172
PA2
Nizam El-Din Session PA2, Thursday 14:15 PA2-35
Swelling and Drug Release Kinetics of Polyacrylamide/Sodium
Alginate Copolymer Hydrogels Synthesized by γ-Irradiation
H. Nizam El-Din1, A. W. El-Naggar1
1National Center for Radiation Research and Technology (NCRRT), Nasr City, Cairo, Egypt
Corresponding Author: H. Nizam El-Din, nizam_eldin@yahoo.com
Hydrophilic hydrogels based on different ratios of polyacrylamide (PAAm) and sodium
alginate (AG) were synthesized by γ-irradiation in aqueous solutions. The pH-sensitive
character of PAAm/AG hydrogels was investigated in a wide range of buffer solutions of
different pH values (2–8). The pH-sensitive character of PAAm/AG hydrogels was utilized
for the possible use in drug delivery; the release profiles of chlortetracycline and ketoprofen,
as drug models, was investigated. The swelling and release were further analyzed by Ficks
power law equation, and the possible mechanisms of the water diffusion and release were
suggested. The hydrogels were characterized by different techniques; FT-IR spectroscopic
analysis, swelling, drug release measurements and kinetics of drug release.
The drug release from loaded PAAm/AG hydrogel films, in different buffer solutions of
pH 2.0, 5 and 8 was studied. Clearly, it can be seen that the drug release from loaded films
is very sensitive to the pH of the medium. The release was increased by increasing the
pH values depending on hydrogel composition. The high the ratio of AG in the hydrogel
composition, the lower was the release. The results were in consistent with the water
swelling ratio of non-loaded PAAm/AG hydrogel films in different pH values. As the
amount of COO´ on alginate is almost equivalent to the amount of NH`3 on PAAm, in the
blank matrix film at pH 2.0, the macromolecular chains in the film matrix attract each other
inducing a shrink in this system. So, the value of water swelling ratio of blank matrix film
was the lowest at pH 2.0. When the equilibrium between the amount of COO´ and NH`3
was broken at high pH, the macromolecule chains of the film matrix toke each other apart,
increasing the water swelling ratio of the film and accelerating the drug release.
Ketoprofen is a non-steroidal anti-inflammatory drug and it has a pKa “ 4.94. The chemical
name for ketoprofen is 2-(3-benzoylphenyl)-propionic acid. When this drug is loaded onto
the networks of PAAm/AG hydrogels, it will be reacted through hydrogen bonding inside
the network structure of hydrogels. These hydrogen bondings are through the COO´ of AG
molecules and those on chemical structure of ketoprofen. For both hydrogel compositions,
ketoprofen released rapidly at first and then gradually reached equilibrium release at „ 3 h
depending on the pH of medium. The equilibrium release of ketoprofen from PAAm/AG
hydrogel (50{50%) is much higher than the release from PAAm/AG hydrogel (80{20%) and
50{50%, irrespective of the pH value. Opposite trends were found in the case of the release
of tetracycline drug at similar conditions.
In this study, films of a new pH-sensitive copolymer hydrogel based on polyacrylamide
(PAAm) and sodium alginate (AG) was successfully prepared by γ-radiation in the form
of interpenetrating polymer networks. The pH-sensitivity of hydrogels affects the drug
release.
IAEA–CN–241–026 395
PA2
PA2-36 Session PA2, Thursday 14:15 Papaléo
Effect of Spatial Confinement on the Radiolytic Efficiency of
High-Energy Ions in Polymers
R. Papaléo1, R. Thomaz1, C. Trautmann2, G. Hoff3, J.-J. Pireaux4, and L. Gutierres1
1Pontifical Catholic University of Rio Grande do Sul, Porto Alegre, Brazil
2GSI Helmholtzzentrum für Schwerionenforschung GmbH, 64291 Darmstadt, Germany
3Instituto Politecnico da Universidade Estadual do Rio de Janeiro, Rio de Janeiro, Brazil
4Université de Namur, 5000 Namur, Belgium
Corresponding Author: R. Papaléo, papaleo@pucrs.br
In this work, the radiolytic efficiency of MeV–GeV heavy ions in polymer thin films has been
quantified, following the induced chemical damage as the layer thickness h of the films
is systematically reduced (2 ă h ă 200 nm). X-ray photoelectron spectroscopy (XPS) was
employed to evaluate bond-breaking in the polymer thin films after ion irradiation. We
evaluated the rate of decrease of C´O and C´Cl XPS peaks in PMMA and PVC films as a
function of the thickness of the polymer layers. Bond breaking cross sections, estimated
from XPS data were found to be insensitive to thickness reductions, even in layers as thin as
5 nm. The damage cross-sections for PMMA were „ 1.5ˆ 10´13 cm2 (for O´C´O bonds)
and „ 2.3ˆ 10´13 cm2 (for C´O bonds) for the 2.2 GeV Bi irradiation, whilst for 2 MeV H
irradiation the values were „ 2.7 ˆ 10´16 cm2 and „ 4.4 ˆ 10´16 cm2, for O´C´O and
C´O bonds, respectively. Meanwhile, PVC damage cross-sections for C´Cl bonds were
estimated as „ 1.5ˆ 10´15 cm2 for 2 MeV H irradiation. These findings indicate that most
of the bond-breaking induced by the ions is related to short-range events close to the track
core. Films thinner than „ 5 nm were difficult to analyze, because of the non-negligible
influence of the adventitious carbon on the substrate, combined to changes caused by the
ion beam (such as roughening and thinning). Our observations are also in contrast to recent
studies showing that surface effects, such as mass transport and cratering formation, are
substantially weakened, when individual ion tracks are confined into polymeric ultra-thin
films due to the suppression of cooperative effects of excited atoms along the ion track.
We will also show results on radial dose profile due to the delta rays in thin water layers
obtained from Monte Carlo simulations with the GEANT-DNA toolkit. Such simulations
provide a first approach to rationalize the impact of film thickness on the energy spread by
the secondary electrons, which is directly coupled to the radiolytic efficiencies.
396 IAEA–CN–241–075
PA2
Pérez Session PA2, Thursday 14:15 PA2-37
Functionalization of Polypropylene Films with Glycidyl
Methacrylate by γ-Radiation
E. Pérez1, G. Burillo1, and A. Ortega1
1Instituto de Ciencias Nucleares, Universidad Nacional Autónoma de México (UNAM), 04510 Ciudad de
México, Mexico
Corresponding Author: E. Pérez, ehrikapvega@gmail.com
Polymeric materials with biologically active components immobilized onto surfaces are
very important for biotechnological and biomedical applications. However, conventional
polymers have no appropriate functional groups (amine, imine, carboxyl, hydroxyl, etc.)
to immobilize biomolecules. Indeed the polymeric surfaces should be modified to intro-
duce such functional groups; although there are many possible routes to functionalize
surfaces, radiation grafting has advantages such as facility in synthesis process and pu-
rification of products, initiators or additives are not necessary, etc. Therefore, a possible
alternative to obtain surfaces rich in amines is carry out the surface modification by γ-
radiation, grafting monomers with functional groups such as primary amino (allylamine),
secondary (acrylamides) and derivatives, which can react with diamines such as hydrazine
or ethylenediamine to obtain free amino groups.
Glycidyl methacrylate (GMA) was grafted onto polypropylene films (PP) using γ-radiation.
Direct and oxidative preirradiation methods were studied. The evaluated parameters were
solvent, monomer concentration, doses, time and temperature. Subsequently, PP-g-GMA
films were reacted with amines (ethylenediamine and hydrazine) to obtain functionalized
films (amines rich surfaces). Different reaction conditions were tested and optimized. The
grafted (PP-g-GMA) and functionalized films were characterized by FTIR, DSC, TGA, angle
contact and swelling behaviour.
GMA was successfully grafted onto PP films using oxidative preirradiation and direct
method. In both procedures were easy to control the graft percentages (10–200%) varying
any parameter such as solvent or dose. The PP-g-GMA was reacted with diamines to
obtain aminated films; the introduction of amine groups was confirmed by monitoring the
disappearance of epoxy group band at 906 cm´1 in FTIR spectra. The radiation grafting
technique can be an easy and quick alternative way to functionalize polymeric materials.
The authors wish to express their thanks to B. Leal, F. García and M. L. Escamilla from ICN
for technical assistance.
IAEA–CN–241–082 Presenter: A. Ortega 397
PA2
PA2-38 Session PA2, Thursday 14:15 Pérez-Calixto
Synthesis and Characterization of PP Films Rich in Primary
Amines for Cell Cultures, by γ-Radiation
M. P. Pérez-Calixto1, G. Burillo1
1Instituto de Ciencias Nucleares, Universidad Nacional Autónoma de México (UNAM), 04510 Ciudad de
México, Mexico
Corresponding Author: M. P. Pérez-Calixto, mitzi.pc07@gmail.com
Development of biomaterials has been increased, due the necessity to find bio-inert materials
able to present a specific cellular response. Biomaterials are very important for tissue
engineering. They can be used as bridges to regenerate damaged tissue growth, as well as
support for immobilized biomolecules (drugs, fungicides, enzymes, etc.). Polymer surface
modification can be carry out by incorporating functional groups on polymeric materials for
the appropriate cell adhesion. It is well known that hydrophobic polymeric surfaces cannot
add cells, however, hydrophilic surfaces, mainly rich in nitrogen, facilitate the adherence.
The amine functional groups (-NH2) are one of the most important for cells and protein
adhesion.
Nowadays, the modification can be carried out by physical or chemical methods. One
of this methods is plasma surface modification, even though is the more common, the
systems synthesized are partly soluble in water, besides the formation of a great amount
of free radicals, which generate the incorporation of oxygen when is in contact with the
air. To overcome this problem, the modified films were synthesized by γ-radiation in a two
step method. In this work, radiation grafting of acryloyl chloride onto polypropylene (PP)
has been applied to insert carboxyl functionalities on PP; and then, the radiation grafted
films were reacted with some diamines. Amine concentration was determined and after
a period of time, the effect of ageing on the amine functional groups was determined by
derivatizationwith 4-trifluoromethyl benzaldehyde (TFBA), and subsequently characterized
by XPS (N/N/C ratios), ATR-FTIR and contact angle.
The authors thank M. Cruz, and A. Ortega for technical support and DGAPA UNAM Grant
IN200116 for financial support.
398 IAEA–CN–241–092
PA2
Piroonpan Session PA2, Wednesday 14:15 PA2-39
Biopolymer-Silver Nanoparticle as a CIELAB Colour Space
Dosimeter
T. Piroonpan1, W. Pasanphan2, and P. Katemake1
1Department of Imaging and Printing Technology, Chulalongkorn University, Bangkok, Thailand
2Kasetsart University, Krung Thep Maha Nakhon 10900, Thailand
Corresponding Author: T. Piroonpan, piroonpan@hotmail.com
A new purpose of silver nanoparticles (AgNPs) in chitosan (CS) biopolymer is proposed as
a radiation dosimeter for application in the dose range of food irradiation. The biopolymer-
AgNPs are simply prepared from AgNO3 precursor and CS (DD “90%,Mv “ 580 kDa)
aqueous solution. The optimum formula of biopolymer-AgNPs dosimeter was studied.
A series of the prepared biopolymer-AgNPs dosimeter relatively response by colour chang-
ing to the electron beam irradiation doses. With this system, the colours were measured in
a CIELAB colour space using a colourimeter. The biopolymer-AgNPs dosimeter is exposed
to various irradiation doses ranging from 0 to 10 kGy. Based on CIELAB colour space, the
colour of biopolymer-AgNPs dosimeter is changed from white to yellow and dark brown by
irradiation. The numerically measured colour is presented in the CIELAB colour difference
(∆Eab). The relationship of dose and colour showed that ∆Eab linearly increased with irra-
diation dose. The colour change is due to the particle size of biopolymer-AgNPs dosimeter.
The colours from the developed biopolymer-AgNPs dosimeter can be applied using general
purpose scanner and the measured colours were then calculated to their corresponding
radiation doses. The biopolymer-AgNPs dosimeter is expected to be a simple, economical,
effective and alternative device as the food irradiation dosimeter.
IAEA–CN–241–214 399
PA2
PA2-40 Session PA2, Thursday 14:15 Pucić
Nanocarbon Based PolyLY(Ethylene-Terephthalate)
Nanocomposites and Various Irradiations
I. Pucić1, V. Borjanović2
1Ruđer Bošković Institute, Zagreb, Croatia
2Faculty of Electrical Engineering and Computing, University of Zagreb, Zagreb, Croatia
Corresponding Author: I. Pucić, pucic@irb.hr
Ionizing and UV radiation produce reactive species in irradiated material. The concen-
tration and distribution of those species depends on the linear energy transfer rate of a
corresponding radiation type. Electromagnetic radiation like γ or X-rays has high penetra-
tion but form relatively few reactive species relatively far apart. Particulate radiations like
protons produce high concentration of ionizations and break many of chemical bonds along
their tracks but have much lower penetration. All ionizing radiation types have enough
energy to break any type of chemical bonds while UV can induce breaking only of some
less stable chemical bonds. The type of radiation and its quantity and dose are not the only
factors that determine the response of polymers and (nano)composites. It depends also on
the chemical structure of the polymer matrix so the overall outcome can be degradation,
cross-linking and/or latent track formation. Poly(ethylene terephthalate) (PET) is widely
used thermoplastic polymer with excellent engineering properties and its radiation stability
is expected increase on addition of appropriate (nano)fillers.
Pure PET film and two of its nanocarbon containing nanocomposite films, one with nano-
diamonds (ND) and thewith other combination of nano-diamonds and graphene nanoplatelets
(NGP) were studied. One group of samples was irradiated with 60Co γ-radiation in ranges
between 0.2 and 1.05 MGy at a dose rate of 2.5 Gy/s, in contact with air. The other group
was irradiated with a 3 MeV proton beam delivered by the 1.0 MV Tandetron (at the flu-
ences of 1014 p/cm2 and 1016 p/cm2) in vacuum. The third group was exposed to UVC
radiation (wavelength 254 nm, the lamp intensity 9 mW). Irradiation effects were studied
using thermal and spectroscopic methods.
Thermal analysis by DSC showed that the crystallinity of PET was just minimally affected
by introduction of nanofillers. Various irradiation types produced different outcomes. DSC
revealed that ordered amorphous phase of irradiated samples was more influenced than its
mobile segment and crystalline was the least affected. Only slight changes were observed in
PET and the nanocomposites irradiated up to 0.5 MGywith γ-irradiation. Proton irradiation
produced much more damage. Graphene containing nanocomposite was more resistant
to proton irradiation than the one containing only nano-diamonds. On the other hand
UV radiation produced the most significant degradation in all samples and particularly in
graphene containing nanocomposite.
The irradiation outcome of PET and its nanocarbon containing nanocomposites depended
primarily on the radiation type while nanofiller had only slight influence. Themost sensitive
part was ordered amorphous phase of PET matrix. All samples were relatively stable to
γ-radiation. Pure PET was significantly degraded by proton irradiation while UV produced
the most degradation in graphene containing nanocomposite.
400 IAEA–CN–241–272
PA2
Raafat Session PA2, Thursday 14:15 PA2-41
In Situ Deposition of Nanohydroxyapatite within
N,O-Carboxymethylchitosan/Polyvinylpyrrolidone Hydrogels:
Characterization and Bioactivity Evaluation
A. Raafat1, E. Hegazy2, E.-S. Soliman3, E. El-Nesr1, and S. Nasef1
1National Center for Radiation Research and Technology (NCRRT), Nasr City, Cairo, Egypt
2Egyptian Atomic Energy Authority (EAEA), Cairo, Egypt
3Chemistry Department, Ain Shams University, Cairo, Egypt
Corresponding Author: A. Raafat, ismaelraafat_a@hotmail.com
Bone is a natural composite; its primary purpose is to provide mechanical support for
soft tissues and serves as an anchor for muscles that generate motion. Although bone
has a remarkable ability to regenerate when damaged, treatment of bone defects from
various causes is still a clinically confusing problem. Of possible choices, autogenous bone
transplantation is the optimum choice. Unfortunately, the limited donor source, the damage
and complications that may happen to the donor site are the worse limitations. Currently,
bone tissue engineering strategies offer promising alternatives for autografts and allografts
using scaffolds for guided tissue regeneration. Scaffolds are synthetic grafts, have the ability
to promote bone regeneration within the defect site. Scaffolds should be porous to ensure
nutrient and waste transport, tissue in-growth, and biological fixation with surrounding
tissue. Also, they should be osteoconductive to facilitate bone formation on its surface.
Scaffold should have adequate mechanical strength to support bone in-growth at the site of
implantation, maintain structural integrity during in vivo tissue remodelling and it should
degrade over time in concert with bone formation. Recently, polymeric composite scaffolds
are gaining increased attention as synthetic alternatives for bone grafting materials. They
improve the bioactivity and mechanical properties so as to meet the basic requirements for
bone repair. The development of bone-like composites with enhanced biocompatibility calls
for a biomimetic approach using hydroxyapatite [Ca10(PO4)6(OH)2] as a guide. Hydrogel
matrices based on N,O carboxymethylchitosan and polyvinylpyrrolidone (NOCMCs/PVP)
were synthesized using γ-radiation as clean initiator. Alternate soaking method was used to
obtain (NOCMCs/PVP)-nanohydroxyapatite composite scaffolds. In vitro bioactivity and
biocompatibility evaluation was investigated before and after immersion in simulated body
fluids (SBF) to follow the formation of bone like carbonated hydroxyapatite (HCA) layers.
After alternate soaking process; the deposition of guided nHA layers onto (NOCMCs/PVP)
hydrogels were confirmed using FTIR, EDX, XRD and SEM techniques. EDX analysis
confirmed that Ca/Pmolar ratio (1.62) was very close to the theoretical value of Ca/Pmolar
ratio in human bone (1.67). The development of nHA crystals was confirmed from XRD
measurements and the average grain size was found to be in the range of 12–37 nm. The
compressive strength for the tested composites recorded comparable values compared to the
cancellous bone. Post immersion in SBF, the growth of carbonated apatite (HCA) particles
increased by time and the surface appears smooth after 28 days of immersion. By increasing
HA content, the weight of blood clot formed and the percent heamolysis decreases and tends
to zero. Synthesis of guided nano-hydroxyapatite layer within (NOCMCs/PVP) hydrogels
using alternate soaking is a simple and efficient method. Biomineralization process in
SBF contributes to the formation of bone like carbonated hydroxyapatite (HCA) layers. In
vitro bioactivity and blood compatibility evaluation indicated that nHA-(NOCMCs/PVP)
scaffold was bioactive and biocompatible and may be promising for bone repair.
IAEA–CN–241–180 401
PA2
PA2-42 Session PA2, Thursday 14:15 Radosavljević
Morphological, Physico-Chemical and Mechanical Properties of
Radiolytically Synthesized Nano-Ag/
poly(N-isopropylacrylamide) Hydrogels
A. Radosavljević1, J. Spasojević1, J. Krstić1, D. Ranković2, P. Milovanović3, M. Ðurić3, and
Z. Kačarević-Popović1
1Vinča Nuclear Institute, University of Belgrade, Belgrade, Serbia
2Faculty of Physical Chemistry, University of Belgrade, Belgrade, Serbia
3Faculty of Medicine, University of Belgrade, Belgrade, Serbia
Corresponding Author: A. Radosavljević, krkljes@vinca.rs
Hydrogels have unique properties and many potential applications, especially in the field
of medicine and biotechnology. The gel porosity and swelling properties, stability and
strength, biodegradability and biocompatibility are characteristics which are widely vari-
able and easily adjusted. Stimuli responsive or intelligent hydrogels are special class of
these materials which shows significant response to small changes in surrounding environ-
ment such as temperature, pH, ionic strength, electric field and light. From a biomedical
point of view, thermo- and pH-sensitive polymers are the most frequently studied. Poly(N-
isopropylacrylamide) (PNiPAAm) is one of the most investigated thermosensitive polymer
with a sharp lower critical solution temperature (LCST) at around 32˝C which can be ad-
justed by copolymerization and/or addition of salts or surfactants to the initial polymer
solution. On the other hand, silver nanoparticles (AgNPs) have been the subject of intense
interest due to their size-dependent optical, catalytic and electronic properties as well as
remarkable antimicrobial potential. AgNPs possess capability to release Ag` ions in a
controlled manner creating powerful antibacterial action for many bacteria. This controlled
release can be provided by incorporation of nanoparticles in cross-linked polymer network.
Among many methods for synthesis of nanocomposites, γ-irradiation induced synthesis
has been recognized as highly suitable tool. In this work, synthesis of nanocomposites was
conducted as two-step process. In the first step, polymerization and cross-linking of polymer
chains occurs and PNiPAAm hydrogels with a large number of pores were obtained. In the
second step, these pores serve as nanoreactors for reduction of Ag` ions and formation of
AgNPs. Absorption spectra of nano-Ag/PNiPAAm hydrogel nanocomposites, with charac-
teristic peaks in the range of 390–415 nm, confirm the successful formation of AgNPs inside
PNiPAAm hydrogel matrix. Morphological analyses (SEM and micro-CT) reveal the exis-
tence of pores with different size, dependent on PNiPAAm concentration, but independent
on incorporation of AgNPs. Structural analysis indicates the presence of spherical AgNPs,
with the mean diameter up to 20 nm and face centred cubic crystal structure. Swelling
processes of investigated systems show thermoresponse with the volume phase transition
temperature (VPTT) between 30.5 and 31.6˝C. The possibility to apply nanocomposites
for controlled release of active silver was investigated by monitoring the release kinetics of
Ag` ions in a buffer solution (pH 7.4) at 25˝C. The results are modelled by applying five
different pharmacokinetic models (Korsmeyer-Peppas, Higuchi, Hixson-Crowel, Kopcha,
and Makoid-Banakar). The best fit solution gave Kopcha and Makoid-Banakar models,
indicating that the release of Ag` ions was predominantly controlled by a diffusion process.
The results obtained from compression measurements shows that mechanical properties of
investigated hydrogels strongly depend on concentration of polymer matrix as well as on
concentration of incorporated AgNPs.
402 IAEA–CN–241–254
PA2
Rahman Session PA2, Thursday 14:15 PA2-43
Preparation of Selective Hazardous Metal Ion Adsorbents from
Acrylic Monomer Grafted PET Films
N. Rahman1
1Bangladesh Atomic Energy Commission (BAEC), Dhaka, Bangladesh
Corresponding Author: N. Rahman, naziabaec@gmail.com
Heavy metal pollution has become one of the most severe environmental problems today.
The well-known environmental destruction cases caused by heavy metals such as Minamata
disease (organic mercury poisoning) and Itai-itai disease (cadmium poisoning) imposed
stricter regulation on the treatment of metal contaminated waste water prior to its discharge
to the environment. In the present study, acrylic monomer grafted polyethylene terephtha-
late (PET) films were prepared and examined for selective adsorption of hazardous heavy
metal.
The γ-ray induced grafting of acrylamide (AAm) and acrylic acid (AAc) onto PET films
were carried out separately. Grafting of AAm and AAc on PET films was characterized
by FTIR and SEM. The grafted films were further modified through alkali hydrolysis to
improve the metal adsorption capacity. The hydrolyzed AAm grafted PET films containing
amide groups were used to study Hg(II) adsorption and the hydrolyzed AAc grafted PET
films containing carboxylate groups were used to study Cu(II) adsorption.
The hydrolyzed AAm grafted PET films were investigated for selective Hg(II) adsorption
from mixture of Hg(II) and Pb(II) and the absorbent film showed high selectivity for the
adsorption of Hg(II) over Pb(II) throughout the entire pH range (2.2–5.6) studied. The
hydrolyzed AAc grafted PET films were used to study the selective Cu(II) adsorption from
mixture of Cu(II), Co(II) and Ni(II) and the adsorbent film showed high selectivity towards
Cu(II) in presence of Cu(II), Co(II) and Ni(II) in the pH range 1.5 to 4.5. Isotherms of
selective metal adsorption were analyzed by using Langmuir isotherm model and kinetics
of selective metal adsorption were investigated using pseudo-first-order and pseudo-second-
order kinetic models. Desorption and reuse of the adsorbent films was also studied. Thus
present study indicated that the functional monomer grafted PET films can be effectively
used for selective adsorption.
IAEA–CN–241–006 403
PA2
PA2-44 Session PA2, Thursday 14:15 Rapado Paneque
Nanogels of Polyvinylpyrrolidone Obtained by γ-Radiation:
Physicochemical and Biological Characterization
M. Rapado Paneque1, A. Ges Naranjo2, and L. Garcia Hernandez1
1Centro de Aplicaciones Tecnológicas y Desarrollo Nuclear (CEADEN), Havana, Cuba
2High Institute for Applied Technologies and Sciences (InSTEC), Havana, Cuba
Corresponding Author: M. Rapado Paneque, rapado@ceaden.edu.cu
Nanogels are nanoscale polymeric matrices with strong affinity for aqueous media. They
exhibit stability, are inert to blood flow and favour the incorporation of medicinal drugs and
bioactivemolecules improving their therapeutic value by increasing bioavailability, solubility
and retention time. The aim of this work was the preparation of polyvinylpyrrolidone
nanogels induced by γ-irradiation, for evaluation as potential drug delivery system.
Experiments were performed in absence of oxygen using diluted aqueous solutions of
PVP. The synthesis was carried out in sealed vials in N2O atmosphere irradiated with
different absorbed doses on a γ-irradiation facility ISOGAMMA LLCo. The nanogels were
characterized by viscometry, spectroscopy (ATR and UV-vis), thermogravimetry (TGA),
X-ray diffraction (XRD), electron microscopy (TEM and SEM), dynamic light scattering.
Cytotoxicity studies were performed by the of NBT and MTT tests.
The viscometric results show a decrease in intrinsic viscosity with increasing dose accom-
panied by an increase in molecular weight. Such behaviour indicates the formation of
intramolecular cross-linking by nanogels. The nanogels have an average size of 50 nm with
a dispersion of 1.04.
The XRD showed certain order in the morphology of the nanogels. Gels are spherical in
shape and have a marked protective effect on cell viability. In the interval of concentrations
studied (0.001–0.8%) the more dilute systems favoured the formation of nanogels, whereas
the more concentrated ones promoted the appearance of microgels IR spectra and thermal
behaviour of nanogels coincided with those of the polymer in bulk. Biological test showed
a high biocompatibility.
Nano PVP gels were obtained using γ-radiation. It was shown that the degree of cross-
linking of the polymer depends on nanogels concentration and the absorbed dose. The
obtained nanogels do not exhibit toxicity to cells, and rather have a protective or stimulator
effect on cell viability, property whichmakes them good candidates as platforms for delivery
systems.
404 IAEA–CN–241–124
PA2
Ratnayake Session PA2, Thursday 14:15 PA2-45
Chemical Reduction of Nitrate by Zerovalent Iron Nanoparticles
Adsorbed Radiation Grafted Copolymer Matrix
S. Y. Ratnayake1, A. K. Ratnayake1, D. Schild2, E. Maczka3, E. Jartych3, J. Luetzenkirchen2,
M. Kosmulski3, and R. Weerasooriya4
1Sri Lanka Atomic Energy Board, Wellampitiya 00900, Sri Lanka
2Karlsruhe Institute of Technology (KIT), Karlsruhe, Germany
3Lublin University of Technology, Lublin, Poland
4University of Peradeniya, Peradeniya, Sri Lanka
Corresponding Author: S. Y. Ratnayake, sanduniratnayake20@gmail.com
Nitrate contamination of global water resources due to the globalization of modern agricul-
tural practices is an emerging threat worldwide. In spite of the usefulness of nitrate and
nitrogenous compounds as essential elements in life processes, nitrate is potentially haz-
ardous when present in drinking water at sufficiently high concentrations. Due to its high
solubility, nitrate may actually be the most widespread and priority contaminant in drinking
water. It acts as a precursor for several health hazards ranging from blue baby syndrome to
gastric cancer. Treatment of nitrate containing water is challenging due to its stability. Re-
duction is the only possible way to fully remove nitrate contamination from ground water as
it does neither form insoluble minerals that could be removed as precipitates nor does it sig-
nificantly adsorb under aquifer conditions. The nitrate molecule is a good electron acceptor
and hence an efficient electron donor is required for its reduction. nZVI can play amajor role
in this situation as it is a good electron donor with a high reactivity due to its extremely small
size and strong reduction capacity. The results obtained in this work suggest that metallic-Fe
can support chemical reduction of nitrate contaminated water. This research specifically
focussed on development of novel methodologies to reduce excess nitrate in drinking water
utilizing nZVI stabilized radiation grafted copolymer matrix. nZVI was synthesized by
borohydrate reduction of FeCl3 and stabilized on a radiation grafted copolymer matrix.
Acrylic acid (AAc) grafted non-woven polyethylene/polypropylene (NWPE/PP-g-AAc)
fabric was used as the supportive copolymer matrix and 60Co γ-radiation was applied. In
previous research, this material has been extensively characterized. The chemical reduction
of nitrate by nZVI adsorbed NWPE/PP-g-AAc (nZVI-Ads-NWP) fabric was examined in
batch experiments at different pH values with the aim of optimizing ammonia production
(ammonia being the major end product) for subsequent conversion to chloroamines upon
chlorination. The pH of the solution showed a marked effect on nitrate reduction with
enhanced efficiency in acidic conditions compared to the micro-scale iron particles. After
about 24 h, at pH 3, almost 96% of nitrate was degraded. According to characterization
data for the material, the surface of the nZVI due to the core-shell structure contains ferrous
hydroxide and other protective layers. At low pH values, these protective layers can be
readily dissolved exposing the pure iron particles for efficient chemical reduction of nitrate.
Experimental results suggest that this reduction process is an acid-driven surface mediated
process. The nZVI water interface has been fully characterized by the 1-pK Basic Stern
Layer Model (BSM) and an Eley-Rideal–like mechanism well described the nitrate reduction
kinetics. In accordance with green technology, newly synthesized nZVI-Ads-NWP has great
potential in designing a nitrate reduction process required in drinking water industry.
IAEA–CN–241–119 405
PA2
PA2-46 Session PA2, Thursday 14:15 Sagatova
Lifetime Study of Electronic Devices for Extreme Radiation
Conditions
A. Sagatova1, M. Fulop1, M. Magyar2, V. Necas3, B. Zatko4, P. Hybler1, and M. Rafaj2
1University Centre of Electron Accelerators, Slovak Medical University, Bratislava, Slovakia
2RMC S.r.o., Nová Dubnica, Slovakia
3Institute of Nuclear and Physical Engineering, Slovak University of Technology, Bratislava, Slovakia
4Institute of Electrical Engineering, Slovak Academy of Sciences, Bratislava, Slovakia
Corresponding Author: A. Sagatova, andrea.sagatova@stuba.sk
Recent boom in radiation technology development and increasing number of its emerging
applications bring new requirements on related devices. Electronic devices connected to all
aspects of our lives today proceed presently with highest speed. However, they are sensitive
to radiation. The study of radiation effect on electronic devices is important for increasing
their lifetime and the reliability of the whole technology, when used in radiation harsh
environment like space, large accelerators, nuclear reactors etc. Our University Centre of
Electron Accelerators (UCEA) is equipped with modern research linear electron accelerator
with X-ray converter. We have studied the effect of both X-rays and high energy electrons
on device lifetime when used in extreme radiation conditions. The CERN accelerator
component was tested by high energy electrons, the semiconductor devices for the first
Slovak satellite were irradiated by X-rays and semiconductor detectors for radiation imaging
and dosimetry were tested by high energy electrons and compared to the experimental
results obtained by their γ-ray and fast neutron irradiation.
The devices were tested at linear electron accelerator UELR-5-1S with scanning pulsed beam
at UCEA in Trenčín, Slovakia with 5 MeV electrons. The repetition rate of the beam pulse
can be set in the range from 5 to 240 Hz, which enables the dose rate to be modified. The
electron beam has been scanning the width of 40 cm and the irradiated object either moved
beneath the scanning beam (CERN accelerator component) or was irradiated in steady
mode (small objects). The CERN accelerator component was irradiated by 5 MeV electrons
up to a dose of 2 MGy, to reveal its most radiation sensitive parts. Various commercial
semiconductor devices for the skCUBE satellite power supply unit were tested by X-rays up
to a dose of 1300 Gy representing the dose obtained by satellite on its orbit duringmore than
3 years. Finally, the semiconductor detectors were irradiated by 5 MeV electrons studying
the effect of radiation of their detection properties and compared to the effects of other
kinds of radiation: fast neutrons and γ-rays.
Our study has proved the functionality of the CERN accelerator component, the engine
for dipole precise positioning, up to 2 MGy. However, plastic parts of the component were
destroyed mechanically and had to be removed in final product. The tested satellite voltage
references exhibited increasing output voltage with applied dose, spoiling the reference
functionality. In the second kind of device degradation, the functionality was preserved, but
the input current dramatically increased (e.g., battery chargers). In the case of semiconductor
detectors, some of their detection properties improved (energy resolution) at small doses
(1–2 kGy) followed by their degradation. However, after 120 kGy dose of electrons, the
detectors were still functional with acceptable detection properties.
406 IAEA–CN–241–392
PA2
Saghatchi Session PA2, Thursday 14:15 PA2-47
The Hormetic Effect of X-Rays on Biosynthesis of Gold
Nanoparticles by Actinobacteria
F. Saghatchi1, M. Salouti2, and G. Jafari1
1Zanjan University of Medical Sciences, Islamic Republic of Iran
2Islamic Azad University, Mashhad, Islamic Republic of Iran
Corresponding Author: F. Saghatchi, hfaranak@yahoo.com
Gold nanoparticles (GNPs) play an important role in medical, health and environmental
applications. All kinds of microorganisms were found to be able to synthesize GNPs. This
study assesses the enhancing effect of low-level X-rays on the biosynthesis of GNPs by
Actinomycetals isolated from Angouran mine in Zanjan province in North West of Iran.
The isolated actinomycetes were grown aerobically in MGYP broth media. The cultures
were centrifuged and the harvested bacteria were suspended in 50 m` aqueous HAuCl4 in
12 Erlenmeyer flasks in 3 groups of 4. Two groups of samples were irradiated by 30 mGy
and 5 mGy X-rays. The third group was considered as control without any radiation. The
solutions were shake-incubated for 120 h.
After five days, the colour of first group samples were changed from milky to purple, while
the colour changing occurred after 10 days in the second group samples and the control
samples. The UV-vis absorption spectrometry of the irradiated aqueous medium by 30 mGy
X-rays confirmed the formation of GNPs.
The findings showed that 30 mGy ionizing radiation stimulated the microorganism to form
GNPs in a half time in comparison to other groups.
IAEA–CN–241–009 407
PA2
PA2-48 Session PA2, Thursday 14:15 Salla Ferreira
Correlation of Traditional and One-Step Irradiation Process for
Chitosan Production from Charybdis Hellerii Crab Shells
M. Salla Ferreira1, E. Moura1, and A. Geraldo1
1Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), São Paulo, Brazil
Corresponding Author: M. Salla Ferreira, maiaraferreira@usp.br
Chitosan is a polysaccharide obtained from chitin’s molecule deacetylation, which is the
main composition of certain fungi species and crustaceans and insects exoskeleton. The
amino groups present in chitosan give it important biological properties such as biodegrad-
ability and biocompatibility, activity/immunological effects and antibacterial healing. The
deacetylation of chitin is an aggressive process, which reaction processes in 6 to 8 h under
hot concentrated alkali solution. In this work, Charybdis hellerii crab shells were fragmented
and pretreated for chitosan production and each conversion step, from in natura material
pretreatment to final chitosan, were investigated in detail. It was observed dose and dose rate
applied as in natura as pretreated chitin influence neither pretreatment process nor chitin
deacetylation step; at 20 kGy (from γ or electron beam sources), the conversion process was
performed in 60 minutes. The obtained chitosan presented low weight and deacetylation
degree compared to standard chitosan, considering specific irradiation conditions.
408 IAEA–CN–241–413
PA2
Sayed Session PA2, Thursday 14:15 PA2-49
Effect of γ-Irradiation on the Molecular Weight and Structure of
Guar Gum
H. Sayed1
1Sudan Atomic Energy Commission, Khartoum, Sudan
Corresponding Author: H. Sayed, huia15@hotmail.com
This work was done in order to evaluate the degradation in polysaccharides structure of
food additives guar gum processed with γ-irradiation. The IR absorbance spectra of the
material prior to irradiation is a good tool tp determine the molecular weight and molecular
weight distribution.
Guar gum samples were irradiated in powder and aqueous solution in two concentration
(1 and 0.5 g/100 m` prepared at room temperature) with different doses (0, 2.5, 5, 7.5, 10,
20, 30, 40 and 50 kGy) of 60Co γ-rays (0 held as control sample). The changes of molecular
weight and structures of the processed samples were investigated and characterized using
Fourier-transform infrared spectra (FTIR), ultraviolet-visible spectral (UV-vis). The results
showed the molecular weight decreased gradually with increasing irradiation dose.
The infrared spectra of the control and irradiated powder were recorded using Ashemaduze
model Fourier transform infrared spectrometer, in the range 4000–350 cm´1. The KBr pellet
technique was adopted for recording the spectra. The solid samples were obtained through
following the procedure of adsorption measurement. Approximately 2 mg of desired
powder sample was thoroughly mixed with 200 mg of spectroscopic grade KBr and pressed
into pellets for recording the spectra. The measurement was carried out by transmittance
scans of dilute solutions of 0.5 and 1% from control, irradiated powder samples and standard
(solutions of 1% Glactose, 1% Mannose) and irradiated solutions concentration (0.5 and
1%) in the wavelength range 250–600 nm.
Results by FTIR and UV-Vis spectra showed that the effect of irradiation on guar gum is
random. Especially with high doses FTIR spectra indicated that γ-irradiation introduced
no significant changes into the structure and crystal texture, but UV spectra showed an
absorption peak at about 265 nm, increasing with irradiation dose, which was attributed to
the formation of carbonyl groups or double bond.
γ-irradiation effects on guar gum properties (chemical and physical) depend on the state
of the gum when irradiated as powder or solution. The effect of the same dose in low
concentrations is more than in high concentrations.
IAEA–CN–241–011 409
PA2
PA2-50 Session PA2, Thursday 14:15 Shayanfar
Investigations on Immobilizing Anthocyanin and Betacyanin
onto Polyethylene Films
S. Shayanfar1, S. Pillai2, P. Cipriano1, S. Talcott1, and V. K. Sharma1
1Texas A&M University, College Station, TX 77840, USA
2National Center for Electron Beam Research, College Station, TX 77845, USA
Corresponding Author: S. Shayanfar, shimika@tamu.edu
The use of plastic polymers for food packaging has increased significantly over the past
decades and the global market for polymers has increased to about 100 million tons today.
Most of the packaging polymers are petroleum-based for cost reasons, ease of application
and worldwide availability. However, besides serving as a physical containment for foods
there is a growing need for food packaging to have additional properties. These include, but
are not limited to, serving as a substrate for antimicrobials and phytochemicals, platform for
sensors to detect food spoilage, food deterioration, pathogen presence, potential deliberate
contamination, as well as physical contaminants such as glass, metal pieces.
Phytochemicals are the secondary metabolites formed in fruits and vegetables that have
a variety of health benefits. Two major phytochemicals present in fruits and vegetables
are anthocyanins and betacyanins. Anthocyanins are a large subclass of flavonoids that
are distinguished for their strong red to blue colour in a variety of fruits and vegetables.
Anthocyanins are potent antioxidants due to their phenolic structure and have antimicrobial
function. We hypothesized that anthocyanin and betacyanin can be grafted directly onto
PE using varying doses on EB and utilizing different types of extracted phytochemicals
(source, and extraction method). We studied the grafting yield as well as the quality and
functionality of the grafted phytochemicals. It is concluded that anthocyanin specifically
when extracted with alcohol has a relatively good stability to high doses of EB even all the
way up to 100 kGy. Anthocyanins can maintain their properties to a considerable degree;
however, betacyanins are not resistant to EB irradiation. Polyethylene is a very strong
and resistant polymer that even a high dose of 1000 kGy does not affect its surface or its
properties. Therefore, polyethylene is not an ideal polymer backbone for grafting organic
and phenolic materials.
410 IAEA–CN–241–230
PA2
Shukri Session PA2, Thursday 14:15 PA2-51
Shelf Life Assessment of Sliced Bread by Sorbic Acid Based
Active Film
N. A. Shukri1, Z. Ghazali1, and M. U. Wahit1
1Universiti Teknologi Malaysia, 81310 Skudai, Johor, Malaysia
Corresponding Author: N. A. Shukri, azwin@nm.gov.my
Food waste and food spoilage is a leading issue facing the world recently. Researchers and
industries have made continuous attempts to discover ways to minimize food spoilage by
making use of active packaging technologies. The development of active food packaging
with antimicrobial functionality enables inhibition of microorganism that caused food
spoilage and thus, extends food shelf life. Radiation-induced grafting has been used in
this study to develop sorbic acid (SA) grafted active film. The SA active film was then use
to investigate the performance of sorbic acid (SA) based active film on shelf-life extension
of sliced bread. The effectiveness of active film against micro-flora formation on bread,
moisture content, weight loss, texture and colour change was elucidated and discussed. The
bread packed with SA active film showed lower in moisture content, weight loss, hardness
and colour change compared to control. Visual observation of bread packed with SA active
film was performed against control film. The SA active film was observed to extend shelf
life of bread up to seven days when compared with the control group, indicating significant
reduction of microbial count.
IAEA–CN–241–103 411
PA2
PA2-52 Session PA2, Thursday 14:15 Spasojević
Structural Characterization, Antibacterial Properties and
Citotoxicity of γ-Irradiation Synthesized
Ag-poly(N-isopropylacrylamide/itaconic acid) Hydrogel
Nanocomposites
J. Spasojević1, A. Radosavljević1, J. Krstić1, M. Mitrić1, P. Milovanović2, M. Ðurić2, and
Z. Kačarević-Popović1
1Vinča Nuclear Institute, University of Belgrade, Belgrade, Serbia
2Faculty of Medicine, University of Belgrade, Belgrade, Serbia
Corresponding Author: J. Spasojević, jelenas@vinca.rs
Silver (Ag) impregnated dressings are intended to promote healing, prevent infection, to
produce a sustained, steady supply of active Ag and to meet the challenges about safety.
Hydrogels impregnated with nanocrystalline Ag (AgNPs) have the potential to meet most
of these requirements. Here hydrogel nanocomposite formulations are based on thermo-
(NiPAAm) and pH-sensitive (IA) copolymer hydrogel matrix doped with AgNPs, (Ag-
P(NiPAAm/IA), as a system for the controlled release of therapeutically active Ag ions
with the aim to obtain the effective smart, antibacterial and nontoxic device. Synthesis of
cross-linked polymer matrix (hydrogel) and in situ incorporation of AgNPs is made by
biocompatible radiolytic products of water (using a 60Co source) which provides a basis for
the wide range of advanced or innovative applications in the biomedical field. The aim of
the work was to investigate structural characteristics of the AgNPs, the micromorphologycal
and physicochemical characteristics of hydrogel, and biomedical potential of γ-irradiation
synthesized nanosystems.
FTIR analysis confirms formation of 3D structure of copolymeric hydrogel with thermo- and
pH responses. Swelling experiment was performed at different temperature (25˝C and 37˝C)
and pH (2.2, 4.5 and 46.8) values. Internal morphology, examined by SEM and micro-CT
analysis, showed the porous structure, dependent on the IA content, while AgNPs have
no influence on the micro-structure. UV-Vis confirmed the synthesis of spherical AgNPs
by the peak at around 400 nm. XRD studies confirmed the face centred cubic (fcc) crystal
structure of AgNPs with the diffraction maxima at 2Θ angle values that correspond to the
Bragg reflections from the crystal planes p111q, p200q, p220q and p311q. The changes of lattice
parameter, interplanar spacing, strain, stress, and dislocation density of crystalline AgNPs
depend on the pore size and the diameter of AgNPs.
The controlled release of active substanceswasmonitored by the release kinetics of Ag ions in
a buffer solution (pH“7.4, T “ 37˝C). The content of Ag ions was determined by Argon arc
plasma and obtained results are modelled by pharmacokinetic models (Korsmeyer-Peppas,
Higuchi, Hixson-Crowel, Kopcha and Makoid-Banakar). Antibacterial potential against
the gram-negative (Escherichia coli) and gram-positive (Staphylococcus aureus) bacteria was
investigated by the disc diffusion and optical density methods. Considering that the basic
condition for the biomedical application of these types of materials is absence of toxicity in
the surrounding tissue, cytotoxicity of synthesized nanocomposite device was examined
by the effect on HaCaT cell line (healthy human keratinocytes). The results show that it is
possible to achieve and fine-tune optimal antibacterial activity, below the cytotoxicity level,
and without any harmful effects on the surrounding cells.
412 Presenter: Z. Kačarević-Popović IAEA–CN–241–256
PA2
Tartaro Bujak Session PA2, Thursday 14:15 PA2-53
The Effect of Natural Antioxidiants in Thiyl Radical-Induced
Lipid Modification Processes
I. Tartaro Bujak1, B. Mihaljević1
1Ruđer Bošković Institute, Zagreb, Croatia
Corresponding Author: I. Tartaro Bujak, itartaro@irb.hr
Polyunsaturated fatty acids (PUFA), major constituents of biological membranes, are sensi-
tive to a free radical attack. The reactions of PUFA with free radicals are known to occur
via two main processes: i) lipid peroxidation, and ii) cis-trans isomerization. Lipid peroxi-
dation can be inhibited by thiols, due to their H-donation ability. On the other hand, thiyl
radicals are known to catalyse the double bond isomerization in PUFA. Both processes have
damaging potential that must be carefully considered for its consequences in a biological
systems. Therefore, the protection against lipid degradation under oxidative and free radical
conditions is of special interest. The aim of this study is to elucidate the influence of different
naturally occurring antioxidants on lipid peroxidation and cis-trans isomerization processes
in biomimetic model system under different conditions.
Model system containing mixed surfactant micelles and buffer was prepared by slow sol-
ubilization of linoleic acid (LH) in non-ionic surfactant micelles previously formed by
mixing Tween®-20 and PB, pH 6.5. The composition of the investigated systems was typ-
ically 0.5 mM LH, 0.28 mM Tween®-20 and 5 mM PB (pH„ 5). Ascorbic acid (AscH),
α-tocopherol and resveratrol (ResOH) of defined concentrations were added during prepa-
ration of model systems. The addition of the amphiphilic 2.8 mM 2-mercaptoethanol was
added to previously preparedmicelles just before irradiation. Model lipid systems were irra-
diated up to the dose of 400 Gy, in equilibriumwith air or after saturation with N2O at room
temperature using panoramic 60Co source at the Ruđer Bošković Institute. Accurate dose
rates in the irradiating positions were established with the ethanol-chlorobenzene dosime-
try system (ISO/ASTM 51538:2009). The concentrations of hydroperoxides of linoleic acid
were determined by the spectrophotometric ferric thiocyanate method, and the geometrical
isomerization of LH methyl ester was studied by capillary gas chromatography.
Under air-equilibrated conditions the addition of different natural occurring antioxidants
retarded the process of lipid peroxidation among which ResOH showed the best antiox-
idative property. In model systems where process of cis-trans isomerization prevailed, the
presence of antioxidants influenced on a decrease of the trans isomerization level; AscH
was the the most effective inhibitor of radiation-induced trans-isomer formation. Among
the natural compounds analyzed in this work an amphiphilic ResOH has proven to be the
most effective antioxidant, also significant inhibitor for cis-trans isomerization process at
the low formation rate of initial radical species.
Results indicate that the cis-trans isomerization and lipid peroxidation processes level could
be dependent on the hydrophilic/lipophilic properties of particular antioxidant and its
localization in model lipid system. This study contributes to the understanding of the role
of antioxidants in radical processes which are not only able to prevent peroxidation but can
also behave as anti-isomerizing compounds.
IAEA–CN–241–208 413
PA2
PA2-54 Session PA2, Thursday 14:15 Ting
Evaluation of Thorium Adsorbent Prepared by Radiation
Grafting and Functionalization with Glucamine
T. M. Ting1
1Malaysian Nuclear Agency, Bangi, 43000 Kajang, Selangor, Malaysia
Corresponding Author: T. M. Ting, tmting@nm.gov.my
Adsorption is considered as themost effective and simplest approaches to separatemetal and
others chemicals from aqueous systems. Activated carbon is one of the most widely used
adsorbents and it can be used to remove almost all pollutants andmetals. However, activated
carbon adsorption suffers from costly regeneration, high attrition rate and low selectivity of
pollutants. Low cost adsorbents with good mechanical strength, high adsorption capacities
and selectivity have attracted increasing interest from researchers to develop a practical
economically adsorbent for separation/extraction of metals. In the past decades, polymeric
adsorbents having ion exchanger property have been identified as potential candidate as
compared to other adsorbents. This is because it has large surface area, excellent mechanical
stability, adjustable surface modification and chemistry, high selectivity and stability after
multiple regeneration cycles. Polymeric adsorbents having fibrous structure have been
found to perform better in term of its adsorption kinetic and capacity. Radiation induced
graft copolymerization is an effective method to prepare adsorbent precursor in fibre form
by grafting of monomer onto the fibre and subsequent functionalization to produce fibrous
polymeric adsorbents.
Thorium adsorbent was prepared by grafting of glycidyl methacrylate (GMA) onto nylon
fibres in methanol mediated grafting system. The degree of grafting was calculated from the
weight gained of fibres before and after grafting. The grafting was carried out by electron
beam irradiation using the preirradiation grafting method. The GMA grafted nylon fibres
were further modified by reaction glucamine. Then, batch adsorption tests were conducted
by adding adsorbent to Erlenmeyer flasks containing thorium solution. The remaining
thorium in the solution was tested using inductively coupled plasma mass spectrometry
(ICP-MS, Agilent 7900) and standard solutions of thorium at 1 ppb, 10 ppb, 100 ppb and
1000 ppb were used to prepare a calibration curve.
Grafting yields of 220% were obtained at 100 kGy absorbed dose, 2 h reaction time, 40˝C
reaction temperature and 10% monomer concentration. The parameters to obtain glucamine
density of 2.2 mmol/g adsorbent were 10% glucamine concentration, 80˝C reaction tem-
perature and 1 h reaction time. The new graft copolymers of GMA and incorporation of
glucamine onto grafted fibres were confirmed by scanning electron microscope (SEM) and
Fourier transform infrared spectroscopy (FT-IR). A thorium adsorbent containing glucamine
functionalized onto GMA grafted nylon-6 was prepared and the maximum adsorption of
thorium was achieved at pH 2. The fibrous adsorbent showed ą98% separation of thorium
from aqueous solution using adsorbent dose of 0.5 g at 50 mg/` thorium concentration, 3 h
reaction time, 30˝C reaction temperature, 200 rpm stirring speed and pH 4.
It can be concluded that the thorium adsorbent having fibrous structure was successfully
prepared and can be applied for thorium separation from aqueous solutions.
414 IAEA–CN–241–013
PA2
Wang Session PA2, Thursday 14:15 PA2-55
γ-Ray-Radiation-Scissioned Chitosan as a Gene Carrier and its
Improved in vitro Gene Transfection Performance
M. Wang1
1University of Science and Technology of China (USTC), Anhui Sheng, Hefei Shi, People’s Republic of China
Corresponding Author: M. Wang, pstwmz@ustc.edu.cn
Chitosan (CS) has long been expected to be an ideal gene carrier for its high biosafety r1s.
However, the low transfection efficiency of the raw chitosan-based vector has long been a
problem troubling the researchers in medicine due to its poor water solubility, low electric
charge density, dissociation problem, and other disadvantages r2s. In this work, CS with
low molecular weight (MW) were prepared through the γ-ray radiation on the acetic acid
solution of CS. The CS chains were scissioned under γ-ray radiation. When the absorbed
dose was above 30 kGy, the MW decreased about an order of magnitude, i.e., from the
original 3.5ˆ 105 g/mol to 9.0ˆ 104 g/mol (30 kGy) and 5.0ˆ 104 g/mol (50 kGy). The
γ-ray-radiation-scissioned CS can effectively bind with plasmid (pEGFP) through complex
coacervationmethod, forming pEGFP/γ-ray-radiation-scissioned CS complex particles with
a size of 200–300 nm. The complex particles has a good stability and little cytotoxicity. The γ-
ray-radiation-scissioned CS can protect pEGFP from being digested by DNase I according to
the gel electrophoresis analysis. The in vitro gene transfection efficiency of the pEGFP/γ-ray-
radiation-scissioned CS complex particles were investigated by fluorescence microscope and
flow cytometry. The results showed that the gene vectors using γ-ray-radiation-scissioned
CS as the carrier will possess better gene transfection efficiency than those using natural
high-MW CS as the carrier. The higher the absorbed dose, the smaller the MW of CS and
the better transfection efficiency of the corresponding gene vector. This work provides a
green and simple method on the preparation of CS-based gene vectors with high efficiency
and biosafety.
References
r1s J. M. Dang and K. W. Leong, Adv. Drug Deliv. Rev., 58, 487 (2006).
r2s S. Mao, W. Sun and T. Kissel, Adv. Drug Deliv. Rev., 62, 12 (2010).
IAEA–CN–241–138 415
PA2
PA2-56 Session PA2, Thursday 14:15 Yin
In Situ Compatibilization of Polyblends and Polymer Based
Composites Induced by γ-Irradiation
Y. Yin1, M. Liu1, and P. Deng1
1Changchun Institute of Applied Chemistry (CIAC), Chinese Academy of Science (CAS), Changchun, People’s
Republic of China
Corresponding Author: Y. Yin, yuany@ciac.ac.cn
Interfacial compatibility is an essential factor for polyblends and polymer based composites,
which is traditionally improved by addition of copolymers with grafting structure or cou-
pling agents, and reactive blending. The generation and recombination of macromolecular
radicals at interface makes γ-irradiation a potential mean to improve the compatibility
of immiscible polymer based multiphase materials. In the present work, polyethylene
terephthalate (PET), polylactic acid (PLA), and nylon based polyblends and composites
were prepared by melt blending, respectively. γ-irradiation in nitrogen atmosphere with
various absorbed dose were employed following sample molding. Morphology, chemical
structure and mechanical property changes were investigated by SEM, FTIR, gel extraction
and mechanical testing. The refinement of the separation particles, the ductile deformation
at cross-section and the rough surface of pull-out fibres indicated the obvious improvement
of compatibility. Gel extraction results and FTIR of the gel confirmed the generation of
grafting polymer containing each component. Mechanical properties were significantly
increased as a result of in situ compatibilization. According to the evidently positive effects
on miscibility found in all multiphase materials, γ-irradiation can be widely-used as an
innovative solution to immiscible materials.
416 IAEA–CN–241–162
PA2
Yun Session PA2, Thursday 14:15 PA2-57
Low Dimensional Nanomaterials-Based Interfacial Engineering
in Organic Solar Cells
J.-M. Yun1, H. B. Kim1, S.-H. Oh1, P.-H. Kang1, and S. Yu1
1Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
Corresponding Author: J.-M. Yun, yjm90@kaeri.re.kr
We have demonstrated a facile but efficient preparation of a solution-processable transition
metal oxide nanoparticles or nanosheets-incorporated reduced graphene oxide (TMONP/
RGO or TMONS/RGO) and excellent organic photovoltaic cells using the TMONP/RGO or
TMONS/RGO to function as a hole extraction layer (HEL). The TMONP/RGO or TMONS/
RGO, featuring uniformly decorated high-quality TMONPs or TMONSs on RGO, can be
synthesized via a simply adding a precursor solution into RGOprepared by an electron beam
irradiation method. Compared with the reference PEDOT:PSS-based cells, the TMONP/
RGO or TMONS/RGO HELs provide superior performance characteristics as a result of
better electrical conductivity and more uniform film quality than that of PEDOT:PSS. In
particular, high performance can be realized irrespective of the thermal treatment conditions
of a solution-processed TMONP/RGO or TMONS/RGO layer, which is a crucial difference
from the previously reported solution-processed metal oxide-based HELs. These results
clearly demonstrate that the TMONP/RGO or TMONS/RGO, prepared by a facile and
efficient method, is a promising hole-transporting material and a potential alternative to
PEDOT:PSS, thus further realizing an efficient and stable OSCs.
IAEA–CN–241–278 Presenter: S. Yu 417
PA2
PA2-58 Session PA2, Thursday 14:15 Zaharescu
Radiochemical Stability and Life Time of LDPE-Based Flexible
Composite Filled with Ce-Doped PZT-PbZrTiO3
T. Zaharescu1, A. Dumitru1, G. Velciu1, V. Marinescu1, D. Panaitescu2, and G. Sbarcea1
1Nuclear Agency and Radioactive Wastes, INCDIE ICPE–CA, Romania
2The National Institute for Research & Development in Chemistry and Petrochemistry (ICECHIM), Bucharest,
Romania
Corresponding Author: T. Zaharescu, traian.zaharescu@icpe-ca.ro
Inorganic compounds like mixed oxides doped with certain low amounts of salts play the
role of stabilizers for many polymer matrices. This property is related to the crystalline
network, where the difference in charge distribution allows the scavenging of new formed
radicals. During the irradiation of polymers the basic processes involve free radicals. They
must not be consumed in parallel reactions as it is occurred in their oxidative degradation.
Under this condition, the doped inorganic phase behaves as an antioxidant. Its protection
activity is similar to the synthesis antioxidants, which delay the decay of free radicals by
their reactions with molecular oxygen.
The preparation of Ce-doped PZT-PbZrTiO3 was accomplished by heat treatment at 920˝C
for 4 h of lead oxide, zirconia and titania with four concentrations (0.25, 0.50, 0.75 and
1.25 w/w%) of cerium chloride. After milling and drying, the powder was added in low
density polyethylene in various proportions (3 and 5 w/w%). The XRD and granulometry
on inorganic compound were done for the depicting the morphological state. The films and
plaqueswere obtained by pressing at 175˝C for 5minutes. γ-irradiationwas accomplished in
air at room temperature in Ob Servo Sanguis (Hungary) 60Co irradiator, whose dose rate was
1.1 kGy/h. The exposure doses were 25, 50, 100 and 200 kGy which were compared with
pristine samples. The stability characterization of modified LDPE samples was performed
by FT-IR spectroscopy, isothermal (190˝C) and nonisothermal (heating rate 10˝C/min)
chemiluminescence and thermal analysis.
The increasing dependence of protection efficiency on the concentration of dopant in inor-
ganic filler explains the participation of these structural defects at the coupling of oxidizable
free radicals. The oxidation state of basic polymer is described by the increases in carbonyl
and hydroxyl indexes, which allow the calculation of the radiochemical yields for these
degradation products. The stabilization effect is related to the surface activity of powder,
whose grain size distribution influences the amplitude of protection.
The factors that influence the stabilization activity and kinetic parameters of oxidative
degradation are doping degree, the filler concentration and the exposure dose, which
determine the interaction probability between solid state defects and free radicals prior their
oxidation. The expected stabilization feature is the required feature for the preservation of
low oxidation level in many organic products like polymers, paints, vanishes, anticorrosive
layers, used in different areas of nuclear units especially nuclear power plants or during
their radiation processing.
418 IAEA–CN–241–155
PA2
Zaouak Session PA2, Thursday 14:15 PA2-59
Decolouration and Degradation of Erythrosine by γ-Irradiation
A. Zaouak1, H. Jelassi1
1National Center for Nuclear Sciences and Technologies (CNSTN), Sidi Thabet, Tunisia
Corresponding Author: A. Zaouak, amirazaouak@gmail.com
In this study, the decolouration and mineralization of aqueous solution of the erythrosine
dye irradiated under γ-rays from 60Co are investigated. From the results of absorption
UV-visible spectra erythrosine solution as function of dose, the concentration of erythrosine
decrease exponentially with increasing γ-irradiation dose and the plot on a logarithmic
scale against the dose shows a clear pseudo-first-order rate. The apparent pseudo-first-order
constant was calculated. The change in decolouration percentage removal of chemical
oxygen demand (COD) and total organic carbon (TOC) were investigated with respect to
the applied dose influences of absorbed doses. Complete mineralization of erythrosine dye
was achieved with γ-irradiation.
IAEA–CN–241–165 419
PA2
PA2-60 Session PA2, Thursday 14:15 Zeng
γ-Ray Induced Reduction and Modification of Graphene Oxide
X. Zeng1, H.-L. Ma2
1Beijing Key Laboratory of Radiation Advanced Materials, Beijing, People’s Republic of China
2Beijing Research Center for Radiation Application,
Beijing Key Laboratory of Radiation Advanced Materials, Beijing, People’s Republic of China
Corresponding Author: X. Zeng, sherry_0282_cn@sina.com
Graphene has attracted increasing attention due to its striking electronic, mechanical and
thermal-conducting properties. Up to now, graphene has been produced by numerous
techniques such as micromechanical exfoliation of graphite, chemical vapour deposition,
epitaxial growth and the reduction of graphene oxide (GO). Among these, the reduction of
GO by γ-ray irradiation has been regarded as the most green, facile and economical method
of the large-scale production of graphene and graphene-based composites.
A series of graphene were prepared by γ-ray induced reduction of GO suspension in dif-
ferent solvents, such as H2O, alcohol, ethylene glycol, N,N-dimethyl formamide (DMF),
N-methylpyrolidone (NMP) and p-phenylene diamine (PPD) aqueous solution. Thermo-
gravimetric analysis (TGA), X-ray photoelectron spectroscopy (XPS) and X-ray diffraction
(XRD) were used to study the structure of GO after γ-ray irradiation. The results show that
GO in these solvents were all reduced. Alkyl groups are attached onto the reduced GO
(RGO) in alcohol or ethylene glycol solution due to the recombination of radicals. Besides,
the protonated amine groups which generated from the radiolysis of DMF, NMP and PPD
are interacted with residual COO´ groups on the edge of the as-synthesized RGO with
the driving force of electrostatic interaction. This work provides a new approach to obtain
different graphene.
420 Presenter: H.-L. Ma IAEA–CN–241–115
PA2
ICARST–2017
PB: Posters PB: Radiation Technologies for
Measurement
421
PB
PB-01 Session PB, Wednesday 14:15 Abdelbari
The Study of Industrial Process with Radioactive Tracer RTD
Method Enhanced System Analysis
A. O. A. Abdelbari1, O. M. E. Alzubair1
1Sudan Atomic Energy Commission, Khartoum, Sudan
Corresponding Author: A. O. A. Abdelbari, amartop@yahoo.com
The radioactive tracer (RTD) method is one of the most common nuclear techniques used for
troubleshooting and optimizing industrial processes involved in different industries such
as petroleum, petrochemicals, chemicals, ore mining, cement and waste water treatment.
The technique is easily implemented with simple concept of instantaneous, so-called Dirac,
impulse response. In the last decades, significant development has been made with the
advent of new equipment, electronics, portable computers and software. However, the
style and quality of the results themselves has not considerably changed since its beginning.
Correct data collection and system analysis, interpretation and reporting are abilities often
difficult to go with or require a long time of training and experience. This paper describes
our attempts on developing a new approach on the radiotracer RTD technique using 99mTc
radiotracer to measure the RTD of closed circuit water flow rig tank. The data was gath-
ered and treated using both Dirac and non-instantaneous impulse. The paper shows and
discusses the comparative results of some experiments conducted.
422 IAEA–CN–241–203
PB
Al-Saedi Session PB, Wednesday 14:15 PB-02
The Concentrations of Major and Trace Elements in Powdered
Milk Using XRF and NAA, and Comparison to Other Techniques
J. K. J. Al-Saedi1
1Ministry of Science and Technology, Baghdad, Iraq
Corresponding Author: J. K. J. Al-Saedi, drjamal40@hotmail.com
Milk and dairy products are considering one of the unique sources for children, and even
adult, nutrition. They are also the source of some vitamins andmanyminerals. Furthermore,
they aremost versatile for natural food in terms of configuration and determine the necessary
components for a healthy life. Milk contains more than twenty different trace elements,
most of them are necessary and very important, such as copper, zinc, manganese and
iron. These elements are the factors involved in many enzymes and play an important
role in many physiological functions. The lack of these elements cause disturbances and
pathological conditions. In addition, it was noted that the increase in the concentrations
of heavy elements such as chromium, cadmium, lead and mercury will cause damage to
human origins, such as kidney and liver, and cause anemia. Furthermore, these inspections
on the heavy elements are of particular concern as milk is largely consumed by infants and
children.
In this study, eight different milk samples were selected from the Iraqi market to measure the
concentrations of major and trace elements. The samples that were selected are most widely
used by Iraqi consumers. These brands are Ankor, Nan, Similac, Nedo, Gold, Novalac,
Kikoz/1 and Kikoz/2.
Different analyzing techniques were used to cover most of the elements that exist in the
samples. Techniques such as X-ray fluorescence (XRF), neutron activation analysis (NAA),
Kjeldahl chemical analyses and atomic absorption spectroscopy (AAS) were employed to
determine the elements and their concentrations. The obtained results were compared with
authorized limit by FAO/WHO standards. Necessary to evaluate the contents of “essential”
and “toxic” heavy metals on a greater number of milk samples from various supplies and
confirm the absence of possible toxicological risks.
IAEA–CN–241–444 423
PB
PB-03 Session PB, Wednesday 14:15 Benahmed
Development of a New Ambient Dosimetry Monitor for In Situ
Environmental Monitoring at the Nuclear Studies Centre of
Maâmora, Morocco
A. Benahmed1, T. Elkhoukhi1, and R. Alami1
1Centre National de l’Energie des Sciences et des Techniques Nucléaires (CNESTEN), Rabat, Morocco
Corresponding Author: A. Benahmed, benahmed@cnesten.org.ma
In this paper, we propose the development of a new data logger system for monitoring the
radiation environment in situ of Morocco nuclear studies centre.
This device is used to measure continuously the γ-dose rate for plotting and monitoring
ambient radioactivity, and equipped with an alert system to alert the operator in cases
which exceed the dose rate threshold limits. It mainly consists of a high-pressure ionization
chamber whose response is directly proportional to the ionization intensity created by the
radiation.
This paper details the development stages of a radiation datalogger which is associated to
a specific monitoring interface for remote measurement of ambient γ-radiation. It starts
first with studying the relationship between the dose rate and the output ionization current
of the HPIC chamber, followed secondly by the development of digital processing unit for
measuring and data recording, and thirdly finishes with the development of a data transfer
module, using an XBee protocol of RF transmission, to the host computer. In addition, this
paper presents also new software which is associated to the datalogger device, used as data
acquisition interface, and was designed and characterized by specific parameters for real
time remote monitoring of γ ambient dosimetry.
In fact, environmental radiation dosimetry has been performed with a high-pressure ioniza-
tion chamber which supplies a current directly proportional to the amount of the incident
particles energy. The output ionization current is of the order of 10´14 A/Gy/h per cubic
decimeter, equivalent to energy absorption of 10 µJ/h and per gramme of the chamber
material. This current is DC coupled first to a preamplifier where it passes through a high
ohmic resistance of 1010 Ω to establish a difference of potential, and followed by a negative
feedback linear amplifier circuit.
The output of this amplifier is then connected to the electronic module for digital data
treatment and transmission to the acquisition software installed into PC.
424 Presenter: R. Alami IAEA–CN–241–277
PB
Broce Session PB, Wednesday 14:15 PB-04
Study of Sediments in a Sub-Basin of the Panama Canal Using
Nuclear Techniques
K. Broce1, R. Pinzón1, I. Arjona1, M. Barragán1, J. Fábrega1, and F. Rivera1
1Universidad Tecnológica de Panamá, Ancón, Panama
Corresponding Author: K. Broce, kathia.broce@utp.ac.pa
In early December 2010 a storm that occurred was named “La Purisima” the largest storm in
the history of the Canal watershed. According to the Panama Canal Authority (ACP, from
Autoridad del Canal de Panamá) Yearbook of suspended sediments for 2010, the storm was
associated with the interaction of a low pressure centre, the remnants of a stationary front
and the intertropical convergence zone in the north-eastern part of the basin of the Panama
Canal. The storm produced a record 760 mm of rain in 24 hours. There were more than
500 landslides in the watershed above the Alajuela dam. These landslides resulted in a large
amount of suspended sediment upstream of this dam, where potable water facilities for
the City of Panama are located. This led to a turbidity of water from the dam of 700 NTU
(nephelometric turbidity units), causing the collapse of the water treatment plant, leaving
a large part of Panama City without drinking water for nearly two months. On the other
hand, waste waters contribute to serious pollution problems not just in Panama Canal basin
but also at the Panama Bay influencing marine and coastal environment, and there is not an
effective monitoring programme for contaminants in treatment plants wastewaters effluent
and coastal marine areas. In addition to this, the sediments are vectors of contaminants such
as heavy metals, etc. The ACPmust operate efficiently and scientifically to collect an analyze
sediments from dredging works (suspension, deposition at some site, etc.) because it is
of fundamental interest to maintain and improve water quality both in the Panama Canal
river basin as in the urban area. Therefore, a characterization of the dynamics of sediment
transport phenomenon using radiotracer and chemical tracers would offer a rigorous and
efficient methodology for a national programme of measurements or monitoring plan of
transport and behaviour of pollutants into resources water of Panama, including the study
of sediments at the biggest Panamanian WWTP.
For sediment transport monitoring, radioactive and chemical tracer technology was selected
because it is a very reliable, accurate and non-intrusive procedure. Its use required low
amounts of radioactive substance. Also, tracers have high resistance to physical factors,
such as temperature and pressure, which make them ideal for this type of studies.
One of the goals of this study is to contribute to reducing the contamination level to in-
ternational water quality standards, through an efficient sediment transport monitoring
programme in the Panama Canal basin and check out the contribution of wastewaters
treated at WWTP to the marine and coastal environments. To achieve this goal, it is nec-
essary to study and compare both methods, non-nuclear and nuclear techniques, using
nucleonic gauge, and comprehend all the processes involved in sediment transport along
the Panama Canal basin, including the contribution of treated waste waters, during dry and
rainy seasons, considering also physic-chemical factors.
IAEA–CN–241–402 425
PB
PB-05 Session PB, Wednesday 14:15 Gichuru
Tracers of High Altitude Pollution Sources and Impact on
Mt. Kenya Ecosystem
M. J. G. Gichuru1, A. W. Mutahi1, and C. W. Gachara1
1Institute of Nuclear Science & Technology, University of Nairobi, Nairobi, Kenya
Corresponding Author: M. J. G. Gichuru, mgatari@uonbi.ac.ke
Tracers of pollution sources have been used in atmospheric studies to track sources of
long distance transported particulate aerosols in the lower and middle troposphere. To
identify the sources of suspected pollutants that are responsible for the degradation of
glaciers on Mt. Kenya the tracers were used in this study. Mt. Kenya is one of the major
sources of water in Kenya and therefore important in sustaining underground and river
water levels. Its ecosystem is therefore important in sustainable economic growth, food
production and poverty eradication. However, Kenya has been experiencing reduction in
river water levels and drying of many wetlands resulting in extended arid lands, especially
in the neighborhood of semiarid areas. Strong winds and convective systems are known
to contribute mineral dust particles in the middle troposphere. This species of aerosol
particles have an estimated lifetime of weeks and can be transported for long distances, for
example the impact of Saharan dust in the Atlantic Ocean and America. The semiarid lands
and increasing anthropogenic activities, especially cultivation, within the fast increasing
population in Kenyawere suspected of impacting onMt. Kenya ecosystem. However, tracing
the sources that contributed to pollution at that altitude remained inhibited due to scanty
measurements in the region. In March 2015, during a period of dry and hot conditions,
which preceded the long rains, a measurement campaign was carried out at a site on the
south-south eastern slopes of Mt. Kenya. The site location is at the equator, at more than
4.7 km above sea level (a.s.l) and is characterized by tropical alpine highland glacier in the
neighborhood of highmountain peaks of heights ranging from 4985 to 5199ma.s.l and lakes.
The campaign mobilized gas and particle monitors, which included a black carbon monitor,
and battery powered particle samplers. Gravimetric measurements of collected airborne
particles on Teflon filter media; the elemental constituents of those particles, glacier snow,
ice and water were used as tracer properties for assessing the source on pollution impacting
the site. Water, snow and ice samples were collected into precleaned plastic containers. The
filter samples were analyzed using convectional EDXRF spectrometer and the samples of
water, snow and ice by TXRF at the Institute of Nuclear Science and Technology, University
of Nairobi, Kenya. On filter samples Ca, Ti, Cr, Mn, Fe, Ni, Cu, Zn and Pb; the abundant
elements were Ca, Ti, Mn, Fe and Zn and in glacier snow, ice and water it wasMn, Ca, Ti and
Fe. These analyzed elements are common tracers of mineral dust thus implicating local and
distance arid lands and anthropogenic activities as sources of pollution that contribute to
the degradation Mt. Kenya ecosystem. However more comprehensive studies are necessary,
despite the difficult terrain and conditions.
426 IAEA–CN–241–279
PB
Goes Nunes Session PB, Wednesday 14:15 PB-06
CaSO4:Dy and CaSO4:Ce,Eu Intrinsic Efficiencies Dependence
on Ionizing Radiation Type and Quality
M. Goes Nunes1, D. Villani1, and L. Luente de Campos Rodrigues1
1Brazilian Nuclear Energy Commission (CNEN), Rio de Janeiro, Brazil
Corresponding Author: M. Goes Nunes, mgnunes@ipen.br
The dependence of a thermoluminescent (TL) dosimeter response to the type and quality
of radiation is a key issue that is being tackled worldwide by the development of new
dosimetric materials associated with this technique. In this context, the aim of the present
work is to evaluate the intrinsic efficiency of CaSO4:Dy, considered as the standard material,
and CaSO4:Ce,Eu, a newly developed TL material, for different ionizing radiation types
and energies. To do so, a batch of 55 dosimeters of each material was selected according
to their non-irradiated TL readout and intrinsic efficiency to the 60Co γ-radiation on air
and electronic equilibrium conditions and then divided into eleven sets of five dosimeters,
one of the sets being kept as the control set to evaluate the non-irradiated TL signal while
the ten remaining sets were irradiated, again in air and electronic equilibrium conditions,
with doses ranging from 0.1 mGy to 10 Gy in secondary standards 60Co and 137Cs γ-
radiation sources, RQR, RQA and RQT ISO/IEC 61267 series and N ISO 4037 series X-ray
beams, always including the reference quality for the radiation beam series, and tertiary
standard collimated electron beamswith effective energies from 4MeV to 20MeV. A Thermo
(Harshaw) 3500 thermoluminescent reader was used to evaluate TL readouts 24 h after
the irradiation and the obtained glow curves were exported in the ASC format through
WinREMS TL reader controller associated software. Individual peak intensity, integrated
response, peak to peak intensity ratio, calibration curves and intrinsic efficiency, provided
that all dosimeters are 0.8 mm thick pellets of 6.0 mm of diameter containing 16.67 mg of
TL material, were calculated with the aid of SciLab 5.5.2 software, also used to graphically
explore the behaviour of CaSO4:Dy and CaSO4:Ce,Eu intrinsic efficiencies with the radiation
type or the radiation quality. As expected from literature, CaSO4:Dy intrinsic efficiency
presented a dependence of up to 30% with radiation type or quality while CaSO4:Ce,Eu
intrinsic efficiency varied by 200% with radiation quality. Despite this huge dependence,
the CaSO4:Ce,Eu peak I to peak II intensity ratio remains stable with the radiation type and
varies by 5% from one radiation type to another, so that this newly developed TL material
can be used as a dosimeter capable of determining, in non-mixed radiation fields and after
an adequate and rigorous calibration, both radiation type and quality besides the dose.
IAEA–CN–241–361 427
PB
PB-07 Session PB, Wednesday 14:15 Khoury Asfora
Evaluation of TL and OSL Response of CaF2:Tm for Electron
Beams Dosimetry in Radiation Processing
V. Khoury Asfora1, P. L. Antonio2, V. Saito M. de Barros1, J. A. Correa Gonçalves2,
M. E. Yamato1, C. C. Bueno2, L. V. E. Caldas2, and H. J. Khoury1
1Depto. de Energia Nuclear, Universidade Federal de Pernambuco, Recife-PE, Brazil
2Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), São Paulo, Brazil
Corresponding Author: V. Khoury Asfora, vikhoury@gmail.com
An increasing number of pytosanitary irradiations using electron beams has encouraged the
development of surface dosimetry systems to copewith both low and intermediate absorbed
doses and dose rates. Besides the well-established reference and routine dosimeters, ranging
from alanine to radiochromic films, there is an interest in dosimeters based on thermolumi-
nescence (TL) and optically stimulated luminescence (OSL) effects. In this context, the aim
of this paper is to study the TL and infrared stimulated luminescence (IRSL) response of
the calcium fluoride dosimeter doped with thulium (CaF2:Tm) produced via combustion
synthesis (CS) by the Nuclear Energy Department of Federal University of Pernambuco,
Brazil. The pellets with 6 mm in diameter and 1 mm thickness were obtained by pressing the
powder using 10% PTFE as binder material. The individual TL and OSL sensitivities of the
dosimeters of the batch were previously evaluated and a group of 50 pellets with a standard
deviation of 6.8% was selected to be used in this study. After that, the performance of these
dosimeters to electron beams with 1.5 MeV from a DC 1500/25/4 – JOB 188 Accelerator
at the Radiation Technology Center at IPEN-CNEN/SP was investigated. For each dose,
four pellets of CaF2:Tm, together with four pellets of alanine were irradiated with doses
from 0.5 kGy up to 10 kGy. The TL and OSL readings were carried out after a preheating at
100˝C during 15 min using a Riso TL/OSL reader, model DA-20. The TL measurements
were taken with a heating rate of 2˝C/s, in the range from 50˝C to 350˝C. The OSL readings
were carried out with infrared stimulation with optical power attenuated to 20% during
240 s. These readings were thermally assisted at 150˝C. Residual thermoluminescent glow
curves for IRSL were recorded after stimulation times.
The reproducibility and stability of the TL and IRSL responses were also evaluated, as well
as the dependence with different dose rates.
The results showed that the main TL peak of the glow is in the region of 200˝C and it was
observed that the IRSL curve of the dosimeters presents a fast and a slow decaying IRSL
signals. The TL and OSL dose response curves were fitted by a second order polynomial
function with correlation coefficients of 0.97 and 0.99, respectively. The results indicated
the possibility of the application of CaF2:Tm for electron beam dosimetry in radiation
processing.
428 Presenter: C. C. Bueno IAEA–CN–241–400
PB
Lopes Gomes Session PB, Wednesday 14:15 PB-08
Radiation Shielding Design Assessment of Nucleonic Gauges
J. D. R. Lopes Gomes1, M. L. Costa1, R. Gomes1, Z. Thomé2, and G. H. Caldas1
1Brazilian Nuclear Energy Commission (CNEN), Rio de Janeiro, Brazil
2Instituto Militar de Engenharia, Rio de Janeiro, Brazil
Corresponding Author: J. D. R. Lopes Gomes, jlopes@cnen.gov.br
In recent years, several standards have been issued by different international committees
specifying requirements for the design of nucleonic gauges taking into account issues related
to radiological protection. For this end, agreement with the standards should be included as
part of the equipment specification of the licencing process, however, most nucleonic gauges
in Brazil were installed in the period prior to the issuance of these international standards.
This study will evaluate the shielding performance of different models of nucleonic gauges,
installed in Brazilian industrial facilities, during operational and maintenance procedures,
taking into account the international standards (ISO/IEC) concerning the constructional
requirements and classification of nucleonic gauges. In Brazil, there are several hundred of
these apparatus installed in at least 500 industrial facilities. Using the information available
from the Brazilian nuclear regulatory body database, it was selected reference industrial
facilities that use a wide range of nucleonic gauges with different radioactive sources and
manufacturers.
In order to assess the shielding performance of nucleonic gauges, the dose equivalent rate
was determined in-loco during operational procedures. Themeasurement protocol took into
account the requirements and procedures proposed by IEC 62598:2011. The maximum dose
equivalent rate was determined at different distances from the nearest accessible surface
using ionization chambers with different detection volumes.
In view of the specific operational conditions found at reference facilities (not covering all
operational situations), the measurements obtained have been used for the validation of a
GEANT4-based Monte Carlo code to allow extrapolations for other operational conditions.
Initially, different designs of nucleonic gauges developed in Brazil were evaluated. The
maximumdose equivalent rate was determined at the reference facility and the designs were
modelled and simulated using the MC. With the dose equivalent rate results for each model,
the nucleonic gauges should be classified into the seven dose rates classes, as specified in
the international standards. It should be noted that, according IEC standard, the equipment
in class one are considered non-compliant with constructional requirements, and should be
retired. The study is still in progress, in order to include other nucleonic gauge models in
use in Brazil. Nucleonic gauges can be subject to extreme environmental conditions such as
high temperatures, salinity, humidity and explosive atmospheres. Aspects of the design
and manufacture of these devices should be treated as an important feature for a proper
approach to radiological protection.
The efficacy of a regulatory system to control radioactive sources is determined by its appro-
priated implementation considering the resources available, normally limited. Therefore
an optimization of resources is needed. The results obtained in this study can enable the
establishment of a safety indicator tool to industrial facilities, taking into account different
designs of nucleonic gauges, so, this additional parameter can be used to determine and to
optimize the frequency of regulatory inspections.
IAEA–CN–241–316 429
PB
PB-09 Session PB, Wednesday 14:15 Lopez Gonzales
Axial Computed Tomography Phase-Space Source Model in the
PenEasy/PENELOPE Monte Carlo System: Implementation and
Validation
A. H. Lopez Gonzales1, L. P. Robayo Puerto1, and P. R. Costa1
1University of São Paulo, São Paulo, Brazil
Corresponding Author: A. H. Lopez Gonzales, ahlopezg@uni.pe
The dosimetric quantities currently adopted by national regulations, or for standardization
of dosimetric models adopted by manufacturers of CT equipment are based on a basic
metric, introduced about thirty years ago: the computed tomography dose index (CTDI).
This quantity, independent of its definition variations, represents the absorbed dose along
the longitudinal axis (central and peripheral) of an acrylic phantom with known and well
defined dimensions. Since the introduction of CTDI as the appropriate metric for deter-
mining the dosimetric characteristics of CT procedures, and its acceptance in the scientific
community and between equipment manufacturers, the technology modified significantly
the architecture of these systems aswell as the clinical procedures for their use. The introduc-
tion of CT cone beam systems, with enlargement of the dimensions of the radiation beams
to accommodation in a small number of rotations of a larger region of interest, brought
significant clinical advantages. However, this expansion of the dimensions of the X-ray
beams used in CT scans and the use of helical techniques, started to make improper the use
of CTDI. As a consequence, the correct assessment of the CTDI through the measurement
of the dose profile along the central and peripheral cylindrical phantom axis has become a
work of crucial importance. Several research groups around the world have been developed
CT dosimetry tools based on the Monte Carlo method. The ImPACT group provides a CT
dosimetry tool based on NRPB SR250 dose distribution data or the use of EGSnrc Monte
Carlo system to assess the dose distribution in cylindrical and anthropomorphic phantoms.
In this work, it will implement an axial computed tomography phase-space source model in
the PenEasy/PENELOPE Monte Carlo system in order to assess the dose spread function
along the z-axis and along a peripheral axis of a cylindrical phantom. The X-ray source
model has been created for a GE Lightspeed CT family, and it considers the tilted anode, the
heel effect and the X-ray spectrum self-attenuation. The phase-space file has been simulated
after the CT collimator and the CT setup includes the construction of the shaper filter
(bowtie filter). Previous result show the primary dose spread function affected by the tilted
anode and by the anode self-attenuation. Finally, the phase-space source model will be
used to simulate an axial and helical scan introducing the table displacement (pitch).
430 IAEA–CN–241–416
PB
Mirsaidov Session PB, Wednesday 14:15 PB-10
Application of Radiation Science and Technology in the
Republic of Tajikistan
U. Mirsaidov1
1Nuclear and Radiation Safety Agency, Dushanbe, Tajikistan
Corresponding Author: U. Mirsaidov, ulmas2005@mail.ru
One of the IAEA National TC Projects having relation to radiation science and technol-
ogy which was successfully implemented in Tajikistan was TAD/8/002 “Creating Non-
Destructive Testing Capability” initiated in 2009. Tajikistan, situated in the one of the
most seismic-affected areas in the world having a number of civil and industrial buildings,
bridges, tunnels, pipelines, hydropower structures, dams and other objects, has only a very
limited knowledge and application of non-destructive testing (NDT). The main objective of
the project TAD/8/002 was to establish facilities for non-destructive testing of industrial
equipment and components as well as for civil engineering structures in accordance with
international standards. Fact-finding expert mission found out the detailed sectors and
industries for the possible use of NDT technique in the country, checked on personnel
availabilities, and visited the possible laboratory buildings. Several meetings with senior
governmental officials were organized, where lectures on NDT for industries, including
civil engineering and special purposes, QAmanagement as well as training and certification
were presented. They aimed in creating awareness among future possible alliances and end-
users of NDT. Necessary equipment to be provided for the laboratory was discussed and
agreed. Echograph with C-software; X-ray generator, both with accessories and software
for civil engineering applications; magneto-anisotropic indicator of mechanical stresses,
model stress vision-with software for 2D and 3D presentations; ultrasonic testing calibra-
tion block with carrying case and certificate; several laboratory equipment, supplies were
purchased. Scientific visits were organized to gain knowledge about the NDT applications
in industry and civil engineering structures, the new and advanced developments in the
field of NDT including the NDT of civil engineering structures. Two group fellowships have
been granted to gain some hands-on experience in the use of the above NDT methods in
industry, acquire training at levels 1 and 2 in the four basic NDTmethods, to familiarize with
standards and procedures for carrying out NDT tests in industry and to take certification
examinations at levels 1 and 2 in the above methods. During the national seminar, presenta-
tions on infrared thermography stress monitor techniques, rebound hammer, carbonation
method, ground penetration radar, ultrasonic techniques, ultrasonic pulse velocity testing
and electromagnetic method were presented. In addition other methods, e.g., the oldest and
most commonly and widest used method visual techniques, was also presented. Training
materials on NDT for industrial and civil engineering safety in Russian language have been
prepared and reviewed. Experts advised on formation of infrastructure for accreditation
and certification of NDT in Tajikistan to meet requirements of international standards. NDT
capability in the country has been developed. Non-destructive testing laboratory has been
created and equipped, personnel properly trained and non-destructive testing procedures
established. Procedures for non-destructive control service have been documented and
established. Tajikistan has now complete know-how, through which industrial and eco-
logical safety can be improved, risk and extended lifetimes of critical components in civil
engineering, transportation, uranium mining and other industries reduced.
IAEA–CN–241–338 431
PB
PB-11 Session PB, Wednesday 14:15 Mohammed
Simulation Studies on the Image Quality of Industrial Film
Radiography
M. S. Mohammed1, E. Banoqitah1
1King Abdulaziz University, Jeddah, Saudi Arabia
Corresponding Author: M. S. Mohammed, msiddeq@gmail.com
This communication highlights investigations aimed to attain a comprehension about the
radiographic non-destructive testing (RT) of water-filled pipes; with the objective of im-
proving the radiographic quality. A radiographic testing computational toolkit was used
to simulate film radiography of a water-filled pipe having an outside diameter of 219 mm
(82), using 192Ir. The results showed that water significantly increases the scattered direct
ratio (SDR) on the film, which results in a poor sensitivity. An approach to decrease the
SDR was examined; and the results indicated prospects to improve the radiographic qual-
ity. Simulation results will be used to set up experiments; to further study the proposed
approach.
432 IAEA–CN–241–066
PB
Myaing Session PB, Wednesday 14:15 PB-12
Comparison of Image Reconstructions for γ-Transmission
Computed Tomography System by Using MATLAB and i-Gorbit
Software
K. N. Myaing1
1Department of Atomic Energy (DAE), Nay Pyi Taw, Myanmar
Corresponding Author: K. N. Myaing, khaing.nm@gmail.com
With wide industrial application, computerized tomography CT is a rapidly developing
technique that is especially useful for imaging and measuring multicomponent and multi-
phase processes. The most important contribution of CT is to greatly improve abilities to
distinguish regions with different γ-ray transmittance and to separate over-lying structures.
The CT system of single source and detector γ-transmission tomography GORBIT, designed
by CANTI, Viet Nam, was used to analyze the different density materials. Hardware of the
GORBIT CT system consists of two servo motors, data logger, computer, a radiation source
and a radiation detector. The measurements in GORBIT system were carried out at the CT
Laboratory in the Department of Atomic Energy, Yangon. This tomography system operates
with a 1.85 GBq (50 mCi) 60Co γ-ray source and a NaI(Tl) scintillation detector. Measured
γ-transmitted data were used to reconstruct the cross-sectional images of research samples.
These images were reconstructed from the measured transmitted data in different image
reconstructions algorithms. Analytical methods of back projection (BP), the filtered back
projection method (FBP) and iterative algorithms of algebraic reconstruction method (ART)
and estimation maximizations (EM) methods were used in i-GORBIT image reconstruction
software. Another image reconstruction programme GCTS was created by using MATLAB
package. In this image reconstruction, different algorithms of back projection (BP) and
filtered back projection (FBP) were used. In FBP method, different filters of Ram-lack filter,
Sheep-Logan, Hamming, Hann and Cosine filter can be chosen and different interpolation
methods can be applied to improve the quality of images. The results of different image
reconstructions programmes were compared and analyzed for the sample materials. In
this research work we will present some results obtained by using tomographic techniques
to analyze various samples to check the distribution of various density materials. These
samples are made by using different properties of materials with high and low density
materials of lead, ion, six holes brick, polymer slab contained in a polymer pipe vessel.
These samples are also used to verify the outcome from the CT analysis with different image
reconstructions programmes i-GORBIT and MATLAB.
IAEA–CN–241–160 433
PB
PB-13 Session PB, Wednesday 14:15 Namburi
Neutron Radiography Studies for Detection of Hydrogen
Distribution in Nuclear Fuel Claddings at Research Centre Řež
H. K. Namburi1, J. Soltes1, M. Marek1, and J. Krejci2
1Research Center Řež (CVR), Řež, Czech Republic
2Ujp Praha a.s., 156 00 Praha-Zbraslav, Czech Republic
Corresponding Author: H. K. Namburi, nab@cvrez.cz
Zirconium (Zr) based nuclear fuel claddings act as a barrier against loss of fuel particles
into the coolant water during plant operation, handling and dry storage of the spent fuel
rods. The claddings absorb hydrogen produced during reactor operation due to water side
corrosion. Increase in the hydrogen (H) concentration limit can lead to hydride precipitation,
resulting in the reduction of cladding strength and/or mechanical failure by a process called
delayed hydride cracking (DHC). The DHC damage mechanism is related and dependent
on the hydrogen concentration, temperature and stress level in the cladding. Therefore,
the distribution and quantification of hydrogen in Zr-based fuel claddings is an object of
intensive research. The high sensitivity of neutrons for hydrogen and as a non-destructive
method, makes neutron radiography a useful technique for detection metal hydrides and
their distribution/location in cladding.
Un-irradiated Zr based fuel clads (Zr-1%Nb) have been investigated at the neutron radiogra-
phy facility of LVR-15 research reactor in Řež, CzechRepublic. The sampleswere investigated
in a horizontal channel that offers an intense thermal neutron beam with a 10 cm diameter.
The facility is equipped with newest Timepix based detectors, with thin 6LiF converters for
neutron detection capable of delivering high resolution. 2D radiography results have been
obtained from three fuel cladding sections that differ in their hydrogen content. Qualitative
information on hydrogen concentration locations in fuel cladding were identified. The
H-distribution was revealed by image processing based on intensity histograms. Based
on the neutron radiography results, quantitative evaluation of hydrides distribution was
performed by classical metallographic procedure and electron microscopy. Qualitative and
quantitative inspection of hydrogen distribution in fuel claddings is reported in this paper.
434 IAEA–CN–241–347
PB
Phirani Session PB, Wednesday 14:15 PB-14
Adsorption Behaviour of Chloroauric Acid, a Generic Adsorbing
Tracer, for Finding Wetting Behaviour of Fluids in Oil and Gas
Industry
J. Phirani1, S. Roy1, and H. J. Pant2
1Indian Institute of Technology, Delhi, India
2Bhabha Atomic Research Centre (BARC), Mumbai, India
Corresponding Author: J. Phirani, jyotiphirani@gmail.com
Tracers are widely used to study physical phenomena taking place inside reactors like
studying the hydrodynamics of the reactor by residence time distribution or characterizing
oil reservoirs for heterogeneity and residual oil saturation. Dual tracer method, which uses
one adsorbing tracer and one nonadsorbing tracer, is used to characterize the reactors for
wetting efficiency of the fluid in gas liquid reactors (trickle bed reactor). Nonadsorbing
tracers are well studied in the literature. Chloroauric acid (HAuCl4 ‚ 3H2O), with 198Au
as γ emitter, is a tracer that adsorbs on the solid surface, therefore can be used as an
adsorbing tracer. It is adsorbed on the surfaces that are easily protonated like silicates
(albite, quartz, feldspar), chitosan, polymers and a wide variety of surfaces. This adsorbing
behaviour makes chloroauric acid a potential generic adsorbing tracer for oil and gas
industry. Glass beads are used in lab scale reactor experiments to form a porous medium.
Therefore, adsorption kinetics and dynamics of chloroauric acid on glass surface will impact
the characterization of the reactor using the two tracer technique. In the present work,
adsorption isotherms and adsorption kinetics of chloroauric acid on glass surface are
studied. The nonradioactive form of chloroauric acid is used for this study which can be
translated to radioactive gold chemical for better accuracy at industrial scale.
UV-visible spectrophotometer, at different wavelengths is used for concentration measure-
ment of nonradioactive chloroauric acid in the chloroauric acid solution. In UV-visible
spectrophotometer, UV or visible rays are passed through the sample. The absorbance of
incident rays of a particular wavelength follows the Beer-Lambert law, and is proportional
to the concentration of chloroauric acid in the sample. Batch adsorption studies are carried
out using glass beads and change in concentration of the solution is measured with time by
UV-Vis spectrophotometer.
The adsorption and desorption behaviour of chloroauric acid on glass beads is obtained for
different tracer concentrations. For chloroauric acid, the pH and chloride ion concentration
are found to impact the adsorption–desorption behaviour on the glass surface. The results
obtained will be used to characterize the lab scale porous medium for wetting efficiency.
IAEA–CN–241–223 435
PB
PB-15 Session PB, Wednesday 14:15 Quaranta
Ion Irradiation Effects on the Optical Properties of Quantum
Dots for Nano-Dosimetric Systems
A. Quaranta1,2, A. Ficorella1,2, M. Dalla Palma1, L. Pancheri1,2, and G. F. Dalla Betta1,2
1Department of Industrial Engineering & TIFPA, University of Trento, Trento, Italy
2INFN, TIFPA, I-38123 Povo, Trento, Italy
Corresponding Author: A. Quaranta, alberto.quaranta@unitn.it
Nowadays it is generally accepted that the radiation damage on cells induced by hadron
beams is related to the track structure, i.e., to the spatial distribution of stochastic interactions
occurring with nanometric volumes.
Luminescent quantum dots (QD) seem to be promising candidates for the realization of
portable systems for the evaluation of the nanodose. Ionization produced in QDs by scat-
tered electrons give rise to quenching or luminescent centres affecting the optical properties
of nanocrystals. So, changes of both luminescence features and excited states lifetimes after
irradiation can be used for evaluation the damage released by ions in nanometric volumes.
In this work, we studied the optical properties of luminescent QDs irradiated with 2.0 MeV
H` proton beams at different fluences. Semiconductor QDs are dispersed into polysiloxane
films at different concentrations on silicon substrates and their luminescence properties are
analyzed before and after the irradiation. During irradiation the light yield is monitored by
means of ion beam induced luminescence (IBIL) measurement. The luminescence bands
are measured with a spectrofluorimeter Jasco FP6300 by exciting the samples at different
wavelength in order to identify possible distribution of emitting centres or size dependent
optical properties. Lifetime measurements are performed with different pulsed lasers, at
355, 405 and 450 nm. The lifetime changes after irradiation are correlatedwith the formation
of quenching centres in QDs.
The results are a proof of concept for the realization of a nanodosimeter based on QD
luminescence properties.
436 IAEA–CN–241–123
PB
Rodríguez Alayón Session PB, Wednesday 14:15 PB-16
Results of Radiation Protection in Practices with Sources of
Ionizing Radiation in the Petroleum Refining Industry
M. Rodríguez Alayón1, R. Peláez Chao1
1Cuvebnpetrol s.a, Cuba
Corresponding Author: M. Rodríguez Alayón, mralayon@cuvenpetrol.cu
Sources of ionizing radiation have wide application in medicine, industry, research, agricul-
ture and education. These sources must be managed in conditions of safety and security.
If used incorrectly or in unsafe conditions, radioactive sources can cause death, serious
injuries and economic losses, as demonstrated by the experience in many areas of the world.
In the oil industry, specifically the oil refining industry has wide application of ionizing
radiation sources in the following fields: 1) Study and control of catalysis. 2) Measure
and control fluid flow. 3) Determination of residence times of liquids in closed systems.
4) Location of interfaces or separation zones of petroleum products circulating in the same
pipe. 5) Analytical determination of components such as sulfur. 6) Studies on corrosion
protection. 7) Fire detection and gas. 8) other
In Cuba three oil refineries are installed in different parts of the country the case in this work
is the Cienfuegos refinery located in the south-central Cuba, specifically in the northern
margin lobe of the Bay of Cienfuegos region. Its purpose is oil refining and product manu-
facturing, purchase, storage, processing, distribution and marketing of oil and petroleum
products within the Cuban territory and abroad.
In the Cienfuegos oil refinery various types of sources of ionizing radiation, linked to the
following practices are used: 1) Location of interfaces or separation zones fixed level nuclear
gauges are usedwith 137Cs, for a total of eight sealed sources, which are used in desalination.
2) Fire detection and gas, ionic smoke detectors used with sources 241Am, for a total of
450 sources, 3) Detection of analytical components, two sulfur analyzers with X-ray tubes.
The above practices have spent more than 8 years in use with very good results. Radiation
protection in the exercise of these was based on the demands and requirements established
by law and national legislation in line with the basic rules and guidelines proposed by the
IAEA internationally.
At the time elapsed they have not reported overdose of occupationally exposed workers, or
specialists and workers related to the exercise of practices, nor have reported incidents or
radiological events.
The results are based on training and training of occupationally exposed workers and
workers linked to practices in the documentation of each and study and exercise plan
radiological emergency linked to other key plans like plan emergency in case of fire and
disaster reduction plan. Training continuity by simple elements such as lectures, conferences,
videos, business web, and internal magazines to the entity raise awareness and training
of workers in confronting possible events and the responsible use of the potential of the
exercise of these practices.
IAEA–CN–241–293 437
PB
PB-17 Session PB, Wednesday 14:15 Sagiroun
Radiation Dosimetry of Laboratory Practices based on
Radiotracers Techniques
M. I. A. Sagiroun1, A. O. A. Abdelbari1
1Sudan Atomic Energy Commission, Khartoum, Sudan
Corresponding Author: M. I. A. Sagiroun, sagiroun005@hotmail.com
Radiotracers techniques have become an important tool for diagnosing industrial reactors
and optimizing processes. Recently, many radiotracer laboratories have been established
aimed at on-the-job training and R&D in the African region with the aid of IAEA TC projects.
This paper shows our efforts in radiation dosimetry, safety, and emergency procedures com-
plying with the regulations of the Sudanese Nuclear and Radiological Regulatory Authority
(SNRRA) for the licencing and commissioning of a radiotracer laboratory. Experiments
using 99mTc 15 GBq radionuclide generator have been conducted in the lab in the presence
of expert radiation inspectors from SNRRA. Radiation monitoring for the workplace has
been done as well as for the surrounding environment. Consequently, personal dosimetry
has been recorded for the radiation workers involved in those experiments. The paper shows
the results of measurements and discusses how optimizing radiation dosimetry, safety has
been achieved during the work.
438 IAEA–CN–241–196
PB
Schoebel Session PB, Wednesday 14:15 PB-18
Application of Complementary Beam Techniques to Study
Deformation Mechanisms in Heterogeneous Materials for
Automotive Industry
M. Schoebel1, J. Bernardi2, and R. Koos1
1FRM2, Technische Universität München, Garching, Germany
2USTEM, Technische Universität Wien, 1040 Vienna, Austria
Corresponding Author: M. Schoebel, michael.schoebel@frm2.tum.de
The increasing demand on power and efficiency in automotive industry increases the
thermo-mechanical loads and power densities in combustion engines. New materials are
required, which combine light weight with sophisticated high temperature strength and
creep resistance to meet the requirements. AlSi and AlCu alloy systems are developed for
structural parts to improve long-term stability and reduce thermal fatigue damage. In such
alloys a composite-like heterogeneous microstructure is formed during casting. The Al2Cu
phase in AlCu systems and Si phase in AlSi systems acts as reinforcement of a soft α-Al
phase. The microstructure morphology (interconnectivity) and the matrix stiffness have
significant influence on stress distributions, deformability and crack formation. Therefore,
not only composition, but also thermal history (i.e., cooling rates after casting and heat
treatments) play an important role for material properties.
Two current projects, the “µ-Fe Sensitivitätsanalyse” and “OptiAlloy” funded by the Bayris-
chen Forschungsstiftung, deal with non-destructive characterization of heterogeneous cast
light alloys by complementary applications of high sophisticated beam techniques. Several
diffraction and imaging experiments were performed to measure microstress (neutron
diffraction), characterize damage initiation and propagation (synchrotron tomography) and
to relate them to the microstructure’s morphology (transmission electron microscopy and
synchrotron tomography). Photons, electrons and neutrons were used as probe particles
according to their interaction with metal and spatial resolution limitations, applicable for
the specific problem.
Neutron diffraction (Stress Spec, FRM2, Garching, Germany) results show elastic and
plastic deformation between the brittle primary phase (AlSi and Al2Cu network) and α-
Al matrix. Big gauge volume and high penetration depths allow in situ acquisition of
strains during high temperature tensile testing. Strain measurements under load and after
unloading were performed to distinguish between micro- and macrostress contributions.
Synchrotron tomography (parallel beam) with absorption contrast imaging of AlCu alloys
and phase contrast imaging of AlSi alloys (low-Z contrast between Al and Si) helps to qualify
microcracks within the microstructure in 3D.
Two independent characteristics could be identified as mainly responsible for crack sensitiv-
ity of AlSi and AlCu alloys: First the morphology of the brittle reinforcing phase (isolated
particles versus interconnected network) as crack inducing parameter and second the duc-
tility of the α-Al matrix (accommodating stresses by plastic deformation) as crack growth
inhibitor.
IAEA–CN–241–216 Presenter: R. Koos 439
PB
PB-19 Session PB, Wednesday 14:15 Sereeter
Neutron Activation Installments for Control of Flour Spar
Enriching Factory in Mongolia
L. Sereeter1, S. Dagva2
1German-Mongolian Institute for Resources and Technology, Ulaanbaatar, Mongolia
2National University of Mongolia, Ulaanbaatar 14200, Mongolia
Corresponding Author: L. Sereeter, lodoysamba@gmail.com
Mongolia is rich in fluorite resources and enriched fluorine is one of items of mineral export
of Mongolia. Sorting fluorite ore on the input of the enriching factory is an important
measure to keep the enrichment process running smoothly. A determination of fluorine
content in the enriching pulp allows fast control of the enriching process. Rapid neutron
activation technique for fluorine content determination in the pulp takes 15 min against the
traditional chemical analysis (one day).
In this paper, devices based on neutron activation technique for fluorine determination in
fluorite ore and enriching pulp in the factory are described. The first device (Flourite-1)
was developed as a stationary instrument for fluorine content determination in the fluorite
ore at mine. The second device (Fluorite-2) was developed to determine fluorine content
in ore on the lorry to sort ores in the factory input. Sorting ore on arrival by its content is
important for enriching process control, as ore to the factory arrives from different mines.
The third device (Fluorite 1M) was developed as stationary (like Fluorite-1) to determine
fluorine content in the enriching pulp to control a enriching process.
All devices use fast neutron activation analysis. Neutron sources 238Pu-Be, 241Am-Be, 252Cf
were used for nuclear reaction 19Fpn, αq16N with measurements based on detecting the
resulting 6.13 MeV γ-ray. Coincident γ-ray of 5.5 MeV and 5.11 Mev are detected which
are released from the samples during the measurement. The 16N half-life is 7.35 s and the
γ-ray intensity is proportional to the fluorine content (CaF2) in the ore or enriching pulp.
Fluorine content is calculated compared with standard samples. Regular 150 ˆ 100 mm
NaI(Tl) γ-ray detectors collect the data.
Fluorite-1 is single channel spectrometry system, where samples and standards are mea-
sured in turn using one counter system. Fluorite-2 is a microprocessor controlled system.
Neutron activation of the ore and γ-ray detection is made by a pneumatic system moving
source and detector to the lorry. Spectrometry amplifier stabilizer was developed as the
detector of device placed outside and amplitude of detector signal was changing depending
on temperature change (temperature range is ´40˝C to `40˝C). Standard 137Cs sources
were used for stabilization, calibration and control of the measuring system. Fluorite-1M
has two counters to count pulses from standard and the samples in each counter, which
allow to reduce time of measurement.
Fluorite 1M had absolute error less than 1% and it was much needed for Bor-Undur, Fluorite
Enriching Factory, Mongolia during the economic crisis years 1990–2000, when there were
shortage of chemical components for chemical analysis of the factory. This kind of device
can be used for control of fluorine enriching factory for industry process control. Especially
this kind of device is needed for purchasing of fluorite ore from individual customers or
export in Mongolia.
440 IAEA–CN–241–008
PB
Smolinski Session PB, Wednesday 14:15 PB-20
Synthesis Method of Multimodal Radiotracers for Industrial
Processes and Environmental Research
T. Smolinski1, P. Wojtowicz1, and A. G. Chmielewski1
1Institute of Nuclear Chemistry and Technology (INCT), Warsaw, Poland
Corresponding Author: T. Smolinski, t.smolinski@ichtj.waw.pl
Radiotracer methodology has been described extensively in the literature. Though radioiso-
topes have been applied to the solution of problems in industry for over 60 years, research
and development of the technology continues unabated. Their role in investigating in-
dustrial problems has been expanding both in routine testing and process research and
development. Extensive experience has been gathered all over the world in application of
radiotracers in industry. There are many reasons for the continuing interest. One of the
most important is industry driven. Multimodal radiotracers with other specific properties
(fluorescent or magnetic properties) are attractive field of investigation. It can be used
for mass transport experiments into copper metallurgy industry. Such studies require the
development of representative tracers in order to follow raw material particles along their
routes of transfer. Second great area of interesting is using radiotracers into environmental
research field. Radiotracers are used primarily to reveal the transport processes, dispersion
and settling of industrial waste in the natural environment. With their limited environmen-
tal impact, radiotracers have the potential to be used in a variety of new applications to
create a wider awareness of the environment and the challenges it faces.
The objective of the work is developing of novel multimodal radiotracers with optical and/or
magnetic properties. Basing on our experience, silica crystals SIO2 have been selected as
a radiotracer matrix. This material is easily obtained by an advanced chemical-ceramic
method called sol-gel process. Gels in the forms of powders were prepared by hydrolysis
and subsequent polycondensation of tetraethoxide/Me nitrate solutions containing ascorbic
acid (ASC) as a catalyst, instead of the HCl or NH4OH routinely used for catalysis in similar
synthesis. During the formation of the silica gel, various metals can be immobilized into
crystal structure of silica particles. The material is sintered and milled. Finally the metal
incorporated into the structure is activated via neutron flux and the radiotracer is ready to
use.
Following our method, we obtained several samples of various radiotracers. As a radiotracer
192Ir was selected. Iridium is easy to activate via neutron flux and the half-life of 192Ir seems
to be acceptable. For obtaining fluorescence or magnetic properties we can use various
additives. The tracer properties were investigated by fluorimeter, magnetic resonance and
γ-spectroscopy.
The advanced radiotracers with combined properties are very unique and can be used for
wide range of applications. Proposed materials can be used for wide range of industrial
and environmental applications. Modified sol-gel process is a suitable and efficient method
for synthesis of this kind of radiotracers.
This work is part of the projects: “Nano-radiotracers with magnetic and fluorescence prop-
erties for labelling of micro-particles of sand and clay.” co-financed by Polish Ministry of
Science and Higher Education and IAEA.
IAEA–CN–241–150 441
PB
PB-21 Session PB, Wednesday 14:15 Sugiharto
Examination the Performance of the Trayed Ethylen Production
Column Using γ-Ray Scan Techique
S. Sugiharto1, W. Wibisono1, and S. Santoso1
1Center for Isotopes and Radiation Application, National Nuclear Energy Agency (BATAN), Jakarta, Indonesia
Corresponding Author: S. Sugiharto, sugi@batan.go.id
The γ-ray scanning technique has been demonstrated to investigate the performance of
trayed column in a petrochemical company. The trayed column is a caustic/water tower of
having diameter of 4.2 m and 40 m height. The multigrid scanning was performed using
70 mCi of 60Co γ source and a scintillation detector. Ten trays, starting from tray #13 at
elevation of 35.050 mm to tray #4 at elevation of 26.950 mm above ground level. Scan data
show that all trays were in their positions. Tray #4 to tray #10 were functioned properly
then carried approximately the same amount of liquid. Light liquid flooding on tray #11
and heavy flooding on tray #12 were identified. Partial flooding was identified on the tray
#13. At the time of shutdown, the scanned data was verified and it was found that the
liquid flooding on the tray #12 was caused by presence of a bucket on that tray, covered
with solidified mud.
442 IAEA–CN–241–158
PB
Sutapa Session PB, Wednesday 14:15 PB-22
Resident Time Determination of IPAG60 in Order to Increase
Efficiency of Drinking Water Treatment Plant for Peatland Area
I. D. A. Sutapa1
1Asia Pacific Centre for Ecohydrology (APCE), UNESCO, Bogor, Indonesia
Corresponding Author: I. D. A. Sutapa, ignasdas@yahoo.co.id
The majority of areas in Riau Province and Middle Kalimantan Province have the land with
peat surfacewater. The characteristics of the peat water are: low pH levels (2–4) that is highly
acidic; high levels of organics; high levels of iron and manganese; yellow or dark brown.
This kind of surface water is basically not suitable as raw water for drinking. Compared
with other surface water that is fresh water, the water from the turf needs to be processed
specifically by adding stages in the process. In order to improve the efficiency of water
treatment plant, it would require a study to determine the resident time of IPAG60. A Li
tracer will be used in this study for the reason of availability, accuracy and ease of use. Peat
water treatment technology that has been established in previous studies allows the peat
areas have peat water treatment facility for drinking water supply. The implementation
and testing of the water treatment facility is limited in the area of Katingan District, Central
Kalimantan province and Bengkalis district, Riau Province, meanwhile, a lot of territory
in some areas in Indonesia, especially Sumatra and Kalimantan, which has a clean water
source issues. Implementation of this technology in the wider area is necessary to support
the increase in water services in the region. The quality of peat water and clean water
(treated by IPAG) indicate that the IPAG can improve peat water quality (class C) into clean
water quality (class A).
IAEA–CN–241–381 443
PB
PB-23 Session PB, Wed. 14:15Weerakkody Appuhamillage
Terrestrial Background Radiation in Norochcholai in the North
Western Coast of Sri Lanka
T. Weerakkody Appuhamillage1, T. Warnakulasuriya2, S. Williams2,
R. Wickremasinghe2, and V. Waduge1
1Sri Lanka Atomic Energy Board, Colombo, Sri Lanka
2Faculty of Medicine, University of Kelaniya, Dalugama, Kelaniya 11600, Sri Lanka
Corresponding Author: T. Weerakkody Appuhamillage, thiwankaweerakkody@gmail.com
Radiation from natural sources are broadly classified into two sources, terrestrial radiation
and extraterrestrial radiation. Terrestrial radiation originates from natural radionuclides
present in rocks, soils, atmosphere, and the hydrosphere. Extraterrestrial radiation or cosmic
radiation having very high energy originates from the sun. Inmost cases, radiation exposure
from natural sources is not harmful to humans but health protection measures need to be
considered. The objective of this study was to assess background radiation in soil, water
and air in a Sri Lankan population (in Norochcholai) living in close proximity to the nuclear
power plant in Kudankulam, India for future monitoring of potential radiation leaks.
Background radiation levels at 1 m height were recorded using a survey meter (automess
dose rate meter 6150AD). Superficial soil samples from 23 locations and water samples
from 15 locations were analyzed by γ-spectrometry. The activity concentration of natural
radionuclides in the soil and water samples were measured by using a HPGe detector
having a relative efficiency of 32.6% with G1 geometry (84 mm diameter, 29 mm height) at
ISO 17025:2005 accredited γ-spectrometry laboratory of the Sri Lanka Atomic Energy Board.
The radioactivity concentrations of 232Th, 40K, 226Ra and 210Pb radionuclides in the soil
and water samples were measured.
The median radioactivity concentrations (range) of 232Th, 40K, 226Ra and 210Pb were
56.0 Bq/kg (16–256 Bq/kg), 96 Bq/kg (62.5–294 Bq/kg) 24 Bq/kg (0.7–83 Bq/kg) and
27 Bq/kg (13–81 Bq/kg), respectively. Mean background radiation level was 0.1 µSv/h.
The γ-ray absorbed dose rates due to 32Th, 40K and 226Ra in soil samples varied between
13.9 nGy/h and 202.8 nGy/h with an average of 61.0 nGy/h which is higher than the global
average of 57 nGy/h. The mean effective dose was 74.9 µSv/y. Radium equivalent activity
ranged from 30.3–458.4 Bq/kg and the mean was 136.5 Bq/kg. In one soil sample the
radium equivalent activity was above 370 which is the cutoff value set by the NEA group of
experts as safe to be used in building materials. The absorbed dose rate did not correlate
with the background radiation levels detected (p “ 0.727). The annual effective dose due to
terrestrial radiation (0.074 mSv/y) was less than the worldwide average of annual effective
dose from natural background radiation due to terrestrial gamma radiation (0.46 mSv/y).
No radioactivity was detected in any of the water samples.
The soil from this study area is safe for use in construction of human dwellings. No radioac-
tivity was detected in water sample.
444 IAEA–CN–241–329
PB
ICARST–2017
Indexes
445
Abstracts by Paper Number
A01-01 . . . . . . . . . . . . . . . . . 82 A09-02 . . . . . . . . . . . . . . . . 140 B02-03. . . . . . . . . . . . . . . . .197
A01-02 . . . . . . . . . . . . . . . . . 83 A09-03 . . . . . . . . . . . . . . . . 141 B02-04 . . . . . . . . . . . . . . . . 198
A01-03 . . . . . . . . . . . . . . . . . 84 A09-04 . . . . . . . . . . . . . . . . 142 B02-05 . . . . . . . . . . . . . . . . 199
A01-04 . . . . . . . . . . . . . . . . . 85 A09-05 . . . . . . . . . . . . . . . . 143 B02-06 . . . . . . . . . . . . . . . . 200
A01-05 . . . . . . . . . . . . . . . . . 86 A09-06 . . . . . . . . . . . . . . . . 144 B03-01 . . . . . . . . . . . . . . . . 202
A01-06 . . . . . . . . . . . . . . . . . 87 A10-01 . . . . . . . . . . . . . . . . 146 B03-02 . . . . . . . . . . . . . . . . 203
A02-01 . . . . . . . . . . . . . . . . . 89 A10-02 . . . . . . . . . . . . . . . . 147 B03-03 . . . . . . . . . . . . . . . . 204
A02-02 . . . . . . . . . . . . . . . . . 90 A10-03 . . . . . . . . . . . . . . . . 148 B03-04 . . . . . . . . . . . . . . . . 205
A02-03 . . . . . . . . . . . . . . . . . 91 A10-04 . . . . . . . . . . . . . . . . 149 B03-05 . . . . . . . . . . . . . . . . 206
A02-04 . . . . . . . . . . . . . . . . . 92 A10-06 . . . . . . . . . . . . . . . . 150 B03-06. . . . . . . . . . . . . . . . .207
A02-05 . . . . . . . . . . . . . . . . . 93 A10-07 . . . . . . . . . . . . . . . . 151 B04-01 . . . . . . . . . . . . . . . . 209
A02-06 . . . . . . . . . . . . . . . . . 94 A11-01 . . . . . . . . . . . . . . . . 153 B04-02 . . . . . . . . . . . . . . . . 210
A03-01 . . . . . . . . . . . . . . . . . 96 A11-02 . . . . . . . . . . . . . . . . 154 B04-03. . . . . . . . . . . . . . . . .211
A03-02 . . . . . . . . . . . . . . . . . 97 A11-03 . . . . . . . . . . . . . . . . 155 B04-04 . . . . . . . . . . . . . . . . 212
A03-03 . . . . . . . . . . . . . . . . . 98 A11-04 . . . . . . . . . . . . . . . . 156 B04-05 . . . . . . . . . . . . . . . . 213
A03-04 . . . . . . . . . . . . . . . . . 99 A11-05 . . . . . . . . . . . . . . . . 157 B04-06 . . . . . . . . . . . . . . . . 214
A03-05 . . . . . . . . . . . . . . . . 100 A12-01 . . . . . . . . . . . . . . . . 159 B04-07 . . . . . . . . . . . . . . . . 215
A03-06 . . . . . . . . . . . . . . . . 101 A12-02 . . . . . . . . . . . . . . . . 160 B05-01. . . . . . . . . . . . . . . . .217
A03-07 . . . . . . . . . . . . . . . . 102 A12-03 . . . . . . . . . . . . . . . . 161 B05-02 . . . . . . . . . . . . . . . . 218
A03-08 . . . . . . . . . . . . . . . . 103 A12-04 . . . . . . . . . . . . . . . . 162 B05-03 . . . . . . . . . . . . . . . . 219
A04-01 . . . . . . . . . . . . . . . . 105 A12-05 . . . . . . . . . . . . . . . . 163 B05-04 . . . . . . . . . . . . . . . . 220
A04-02 . . . . . . . . . . . . . . . . 106 A12-06 . . . . . . . . . . . . . . . . 164 B05-05. . . . . . . . . . . . . . . . .221
A04-03 . . . . . . . . . . . . . . . . 107 A13-01 . . . . . . . . . . . . . . . . 166 B05-06 . . . . . . . . . . . . . . . . 222
A04-04 . . . . . . . . . . . . . . . . 108 A13-02 . . . . . . . . . . . . . . . . 167 B06-01 . . . . . . . . . . . . . . . . 224
A04-05 . . . . . . . . . . . . . . . . 109 A13-03 . . . . . . . . . . . . . . . . 168 B06-02 . . . . . . . . . . . . . . . . 225
A05-01 . . . . . . . . . . . . . . . . 111 A13-04 . . . . . . . . . . . . . . . . 169 B06-03 . . . . . . . . . . . . . . . . 226
A05-02 . . . . . . . . . . . . . . . . 112 A13-05 . . . . . . . . . . . . . . . . 170 B06-04. . . . . . . . . . . . . . . . .227
A05-03 . . . . . . . . . . . . . . . . 113 A13-06 . . . . . . . . . . . . . . . . 171 B06-05 . . . . . . . . . . . . . . . . 228
A05-04 . . . . . . . . . . . . . . . . 114 A13-07 . . . . . . . . . . . . . . . . 172 B07-01 . . . . . . . . . . . . . . . . 230
A05-05 . . . . . . . . . . . . . . . . 115 A14-01 . . . . . . . . . . . . . . . . 174 B07-02. . . . . . . . . . . . . . . . .231
A05-06 . . . . . . . . . . . . . . . . 116 A14-02 . . . . . . . . . . . . . . . . 175 B07-03 . . . . . . . . . . . . . . . . 232
A05-07 . . . . . . . . . . . . . . . . 117 A14-03 . . . . . . . . . . . . . . . . 176 B07-04 . . . . . . . . . . . . . . . . 233
A06-01 . . . . . . . . . . . . . . . . 119 A14-04 . . . . . . . . . . . . . . . . 177 B07-05 . . . . . . . . . . . . . . . . 234
A06-02 . . . . . . . . . . . . . . . . 120 A14-05 . . . . . . . . . . . . . . . . 178 B07-06 . . . . . . . . . . . . . . . . 235
A06-03 . . . . . . . . . . . . . . . . 121 A14-06 . . . . . . . . . . . . . . . . 179 B08-01. . . . . . . . . . . . . . . . .237
A06-04 . . . . . . . . . . . . . . . . 122 A15-01 . . . . . . . . . . . . . . . . 181 B08-02 . . . . . . . . . . . . . . . . 238
A06-05 . . . . . . . . . . . . . . . . 123 A15-02 . . . . . . . . . . . . . . . . 182 B08-03 . . . . . . . . . . . . . . . . 239
A07-01 . . . . . . . . . . . . . . . . 125 A15-03 . . . . . . . . . . . . . . . . 183 B08-04 . . . . . . . . . . . . . . . . 240
A07-02 . . . . . . . . . . . . . . . . 126 A15-04 . . . . . . . . . . . . . . . . 184 B08-05. . . . . . . . . . . . . . . . .241
A07-03 . . . . . . . . . . . . . . . . 127 A15-05 . . . . . . . . . . . . . . . . 185 B09-01 . . . . . . . . . . . . . . . . 243
A07-04 . . . . . . . . . . . . . . . . 128 A15-06 . . . . . . . . . . . . . . . . 186 B09-02 . . . . . . . . . . . . . . . . 244
A07-05 . . . . . . . . . . . . . . . . 129 A15-07 . . . . . . . . . . . . . . . . 187 B09-03 . . . . . . . . . . . . . . . . 245
A07-06 . . . . . . . . . . . . . . . . 130 B09-04 . . . . . . . . . . . . . . . . 246
A08-01 . . . . . . . . . . . . . . . . 132 B01-01 . . . . . . . . . . . . . . . . 189 B09-05. . . . . . . . . . . . . . . . .247
A08-02 . . . . . . . . . . . . . . . . 133 B01-02 . . . . . . . . . . . . . . . . 190 B09-06 . . . . . . . . . . . . . . . . 248
A08-03 . . . . . . . . . . . . . . . . 134 B01-03. . . . . . . . . . . . . . . . .191 B10-01 . . . . . . . . . . . . . . . . 250
A08-04 . . . . . . . . . . . . . . . . 135 B01-04 . . . . . . . . . . . . . . . . 192 B10-02. . . . . . . . . . . . . . . . .251
A08-05 . . . . . . . . . . . . . . . . 136 B01-05 . . . . . . . . . . . . . . . . 193 B10-03 . . . . . . . . . . . . . . . . 252
A08-06 . . . . . . . . . . . . . . . . 137 B02-01 . . . . . . . . . . . . . . . . 195 B10-04 . . . . . . . . . . . . . . . . 253
A09-01 . . . . . . . . . . . . . . . . 139 B02-02 . . . . . . . . . . . . . . . . 196 B10-05 . . . . . . . . . . . . . . . . 254
446
ICARST–2017
B11-01 . . . . . . . . . . . . . . . . 256 PA1-17 . . . . . . . . . . . . . . . . 313 PA2-09 . . . . . . . . . . . . . . . . 368
B11-02. . . . . . . . . . . . . . . . .257 PA1-18 . . . . . . . . . . . . . . . . 314 PA2-10 . . . . . . . . . . . . . . . . 369
B11-03 . . . . . . . . . . . . . . . . 258 PA1-19 . . . . . . . . . . . . . . . . 315 PA2-11 . . . . . . . . . . . . . . . . 370
B11-04 . . . . . . . . . . . . . . . . 259 PA1-20 . . . . . . . . . . . . . . . . 316 PA2-12 . . . . . . . . . . . . . . . . 372
B11-05 . . . . . . . . . . . . . . . . 260 PA1-21 . . . . . . . . . . . . . . . . 317 PA2-13 . . . . . . . . . . . . . . . . 373
B11-06. . . . . . . . . . . . . . . . .261 PA1-22 . . . . . . . . . . . . . . . . 318 PA2-14 . . . . . . . . . . . . . . . . 374
B12-01 . . . . . . . . . . . . . . . . 263 PA1-23 . . . . . . . . . . . . . . . . 319 PA2-15 . . . . . . . . . . . . . . . . 375
B12-02 . . . . . . . . . . . . . . . . 264 PA1-24 . . . . . . . . . . . . . . . . 320 PA2-16 . . . . . . . . . . . . . . . . 376
B12-03 . . . . . . . . . . . . . . . . 265 PA1-25 . . . . . . . . . . . . . . . . 321 PA2-17 . . . . . . . . . . . . . . . . 377
B12-04 . . . . . . . . . . . . . . . . 266 PA1-26 . . . . . . . . . . . . . . . . 322 PA2-18 . . . . . . . . . . . . . . . . 378
B12-05. . . . . . . . . . . . . . . . .267 PA1-27 . . . . . . . . . . . . . . . . 323 PA2-19 . . . . . . . . . . . . . . . . 379
B12-06 . . . . . . . . . . . . . . . . 268 PA1-28 . . . . . . . . . . . . . . . . 324 PA2-20 . . . . . . . . . . . . . . . . 380
B13-01 . . . . . . . . . . . . . . . . 270 PA1-29 . . . . . . . . . . . . . . . . 325 PA2-21 . . . . . . . . . . . . . . . . 381
B13-02. . . . . . . . . . . . . . . . .271 PA1-30 . . . . . . . . . . . . . . . . 326 PA2-22 . . . . . . . . . . . . . . . . 382
B13-03 . . . . . . . . . . . . . . . . 272 PA1-31 . . . . . . . . . . . . . . . . 327 PA2-23 . . . . . . . . . . . . . . . . 383
B13-04 . . . . . . . . . . . . . . . . 273 PA1-32 . . . . . . . . . . . . . . . . 328 PA2-24 . . . . . . . . . . . . . . . . 384
B13-05 . . . . . . . . . . . . . . . . 274 PA1-33 . . . . . . . . . . . . . . . . 329 PA2-25 . . . . . . . . . . . . . . . . 385
B14-01 . . . . . . . . . . . . . . . . 276 PA1-34 . . . . . . . . . . . . . . . . 330 PA2-26 . . . . . . . . . . . . . . . . 386
B14-02. . . . . . . . . . . . . . . . .277 PA1-35 . . . . . . . . . . . . . . . . 331 PA2-27 . . . . . . . . . . . . . . . . 387
B14-03 . . . . . . . . . . . . . . . . 278 PA1-36 . . . . . . . . . . . . . . . . 332 PA2-28 . . . . . . . . . . . . . . . . 388
B14-04 . . . . . . . . . . . . . . . . 279 PA1-37 . . . . . . . . . . . . . . . . 333 PA2-29 . . . . . . . . . . . . . . . . 389
B14-05 . . . . . . . . . . . . . . . . 280 PA1-38 . . . . . . . . . . . . . . . . 334 PA2-30 . . . . . . . . . . . . . . . . 390
B14-06. . . . . . . . . . . . . . . . .281 PA1-39 . . . . . . . . . . . . . . . . 335 PA2-31 . . . . . . . . . . . . . . . . 391
B14-07 . . . . . . . . . . . . . . . . 282 PA1-40 . . . . . . . . . . . . . . . . 336 PA2-32 . . . . . . . . . . . . . . . . 392
B15-01 . . . . . . . . . . . . . . . . 284 PA1-41 . . . . . . . . . . . . . . . . 337 PA2-33 . . . . . . . . . . . . . . . . 393
B15-02 . . . . . . . . . . . . . . . . 285 PA1-42 . . . . . . . . . . . . . . . . 338 PA2-34 . . . . . . . . . . . . . . . . 394
B15-03 . . . . . . . . . . . . . . . . 286 PA1-43 . . . . . . . . . . . . . . . . 339 PA2-35 . . . . . . . . . . . . . . . . 395
B15-04. . . . . . . . . . . . . . . . .287 PA1-44 . . . . . . . . . . . . . . . . 340 PA2-36 . . . . . . . . . . . . . . . . 396
B15-05 . . . . . . . . . . . . . . . . 288 PA1-45 . . . . . . . . . . . . . . . . 341 PA2-37 . . . . . . . . . . . . . . . . 397
B15-06 . . . . . . . . . . . . . . . . 289 PA1-46 . . . . . . . . . . . . . . . . 342 PA2-38 . . . . . . . . . . . . . . . . 398
B16-01. . . . . . . . . . . . . . . . .291 PA1-47 . . . . . . . . . . . . . . . . 343 PA2-39 . . . . . . . . . . . . . . . . 399
B16-02 . . . . . . . . . . . . . . . . 292 PA1-48 . . . . . . . . . . . . . . . . 344 PA2-40 . . . . . . . . . . . . . . . . 400
B16-03 . . . . . . . . . . . . . . . . 293 PA1-49 . . . . . . . . . . . . . . . . 345 PA2-41 . . . . . . . . . . . . . . . . 401
B16-04 . . . . . . . . . . . . . . . . 294 PA1-50 . . . . . . . . . . . . . . . . 346 PA2-42 . . . . . . . . . . . . . . . . 402
B16-05 . . . . . . . . . . . . . . . . 295 PA1-51 . . . . . . . . . . . . . . . . 347 PA2-43 . . . . . . . . . . . . . . . . 403
PA1-52 . . . . . . . . . . . . . . . . 348 PA2-44 . . . . . . . . . . . . . . . . 404
OP-04 . . . . . . . . . . . . . . . . . . 80 PA1-53 . . . . . . . . . . . . . . . . 349 PA2-45 . . . . . . . . . . . . . . . . 405
PA1-54 . . . . . . . . . . . . . . . . 350 PA2-46 . . . . . . . . . . . . . . . . 406
PA1-01 . . . . . . . . . . . . . . . . 297 PA1-55 . . . . . . . . . . . . . . . . 351 PA2-47 . . . . . . . . . . . . . . . . 407
PA1-02 . . . . . . . . . . . . . . . . 298 PA1-56 . . . . . . . . . . . . . . . . 352 PA2-48 . . . . . . . . . . . . . . . . 408
PA1-03 . . . . . . . . . . . . . . . . 299 PA1-57 . . . . . . . . . . . . . . . . 353 PA2-49 . . . . . . . . . . . . . . . . 409
PA1-04 . . . . . . . . . . . . . . . . 300 PA1-58 . . . . . . . . . . . . . . . . 354 PA2-50 . . . . . . . . . . . . . . . . 410
PA1-05 . . . . . . . . . . . . . . . . 301 PA1-59 . . . . . . . . . . . . . . . . 355 PA2-51 . . . . . . . . . . . . . . . . 411
PA1-06 . . . . . . . . . . . . . . . . 302 PA1-60 . . . . . . . . . . . . . . . . 356 PA2-52 . . . . . . . . . . . . . . . . 412
PA1-07 . . . . . . . . . . . . . . . . 303 PA1-61 . . . . . . . . . . . . . . . . 357 PA2-53 . . . . . . . . . . . . . . . . 413
PA1-08 . . . . . . . . . . . . . . . . 304 PA1-62 . . . . . . . . . . . . . . . . 358 PA2-54 . . . . . . . . . . . . . . . . 414
PA1-09 . . . . . . . . . . . . . . . . 305 PA2-01 . . . . . . . . . . . . . . . . 360 PA2-55 . . . . . . . . . . . . . . . . 415
PA1-10 . . . . . . . . . . . . . . . . 306 PA2-02 . . . . . . . . . . . . . . . . 361 PA2-56 . . . . . . . . . . . . . . . . 416
PA1-11 . . . . . . . . . . . . . . . . 307 PA2-03 . . . . . . . . . . . . . . . . 362 PA2-57 . . . . . . . . . . . . . . . . 417
PA1-12 . . . . . . . . . . . . . . . . 308 PA2-04 . . . . . . . . . . . . . . . . 363 PA2-58 . . . . . . . . . . . . . . . . 418
PA1-13 . . . . . . . . . . . . . . . . 309 PA2-05 . . . . . . . . . . . . . . . . 364 PA2-59 . . . . . . . . . . . . . . . . 419
PA1-14 . . . . . . . . . . . . . . . . 310 PA2-06 . . . . . . . . . . . . . . . . 365 PA2-60 . . . . . . . . . . . . . . . . 420
PA1-15 . . . . . . . . . . . . . . . . 311 PA2-07 . . . . . . . . . . . . . . . . 366 PB-01 . . . . . . . . . . . . . . . . . 422
PA1-16 . . . . . . . . . . . . . . . . 312 PA2-08 . . . . . . . . . . . . . . . . 367 PB-02 . . . . . . . . . . . . . . . . . 423
447
ICARST–2017
PB-03 . . . . . . . . . . . . . . . . . 424 PB-10 . . . . . . . . . . . . . . . . . 431 PB-17 . . . . . . . . . . . . . . . . . 438
PB-04 . . . . . . . . . . . . . . . . . 425 PB-11 . . . . . . . . . . . . . . . . . 432 PB-18 . . . . . . . . . . . . . . . . . 439
PB-05 . . . . . . . . . . . . . . . . . 426 PB-12 . . . . . . . . . . . . . . . . . 433 PB-19 . . . . . . . . . . . . . . . . . 440
PB-06 . . . . . . . . . . . . . . . . . 427 PB-13 . . . . . . . . . . . . . . . . . 434 PB-20 . . . . . . . . . . . . . . . . . 441
PB-07 . . . . . . . . . . . . . . . . . 428 PB-14 . . . . . . . . . . . . . . . . . 435 PB-21 . . . . . . . . . . . . . . . . . 442
PB-08 . . . . . . . . . . . . . . . . . 429 PB-15 . . . . . . . . . . . . . . . . . 436 PB-22 . . . . . . . . . . . . . . . . . 443
PB-09 . . . . . . . . . . . . . . . . . 430 PB-16 . . . . . . . . . . . . . . . . . 437 PB-23 . . . . . . . . . . . . . . . . . 444
448
Contributions by Indico Submission Number
IAEA–CN–249–001 . . . . 392 IAEA–CN–249–068 . . . . 122 IAEA–CN–249–143 . . . . 168
IAEA–CN–249–002 . . . . 224 IAEA–CN–249–069 . . . . 116 IAEA–CN–249–145 . . . . 134
IAEA–CN–249–003 . . . . 102 IAEA–CN–249–070 . . . . 245 IAEA–CN–249–146 . . . . 326
IAEA–CN–249–006 . . . . 403 IAEA–CN–249–071 . . . . 330 IAEA–CN–249–147 . . . . 159
IAEA–CN–249–007 . . . . . 91 IAEA–CN–249–072 . . . . 337 IAEA–CN–249–148 . . . . 205
IAEA–CN–249–008 . . . . 440 IAEA–CN–249–073 . . . . 308 IAEA–CN–249–149 . . . . 238
IAEA–CN–249–009 . . . . 407 IAEA–CN–249–074 . . . . 273 IAEA–CN–249–150 . . . . 441
IAEA–CN–249–010 . . . . 137 IAEA–CN–249–075 . . . . 396 IAEA–CN–249–151 . . . . 333
IAEA–CN–249–011 . . . . 409 IAEA–CN–249–079 . . . . . 94 IAEA–CN–249–152 . . . . 357
IAEA–CN–249–013 . . . . 414 IAEA–CN–249–082 . . . . 397 IAEA–CN–249–153 . . . . 211
IAEA–CN–249–016 . . . . 317 IAEA–CN–249–083 . . . . 336 IAEA–CN–249–154 . . . . 344
IAEA–CN–249–018 . . . . 218 IAEA–CN–249–084 . . . . 349 IAEA–CN–249–155 . . . . 418
IAEA–CN–249–019 . . . . 217 IAEA–CN–249–085 . . . . 328 IAEA–CN–249–156 . . . . 334
IAEA–CN–249–020 . . . . 228 IAEA–CN–249–086 . . . . 299 IAEA–CN–249–157 . . . . 206
IAEA–CN–249–021 . . . . 227 IAEA–CN–249–087 . . . . 106 IAEA–CN–249–158 . . . . 442
IAEA–CN–249–022 . . . . 232 IAEA–CN–249–088 . . . . 271 IAEA–CN–249–159 . . . . 331
IAEA–CN–249–023 . . . . 235 IAEA–CN–249–092 . . . . 398 IAEA–CN–249–160 . . . . 433
IAEA–CN–249–024 . . . . 132 IAEA–CN–249–093 . . . . 306 IAEA–CN–249–162 . . . . 416
IAEA–CN–249–026 . . . . 395 IAEA–CN–249–094 . . . . 103 IAEA–CN–249–163 . . . . 162
IAEA–CN–249–027 . . . . 292 IAEA–CN–249–101 . . . . 318 IAEA–CN–249–164 . . . . 101
IAEA–CN–249–028 . . . . 231 IAEA–CN–249–102 . . . . 135 IAEA–CN–249–165 . . . . 419
IAEA–CN–249–029 . . . . 263 IAEA–CN–249–103 . . . . 411 IAEA–CN–249–166 . . . . 319
IAEA–CN–249–031 . . . . 203 IAEA–CN–249–105 . . . . 367 IAEA–CN–249–167 . . . . 366
IAEA–CN–249–032 . . . . 302 IAEA–CN–249–106 . . . . 151 IAEA–CN–249–169 . . . . 361
IAEA–CN–249–033 . . . . 139 IAEA–CN–249–107 . . . . 356 IAEA–CN–249–170 . . . . 375
IAEA–CN–249–034 . . . . 274 IAEA–CN–249–108 . . . . 312 IAEA–CN–249–172 . . . . 394
IAEA–CN–249–035 . . . . 332 IAEA–CN–249–111 . . . . 305 IAEA–CN–249–175 . . . . 212
IAEA–CN–249–036 . . . . 377 IAEA–CN–249–113 . . . . 244 IAEA–CN–249–176 . . . . 260
IAEA–CN–249–037 . . . . 136 IAEA–CN–249–114 . . . . 342 IAEA–CN–249–178 . . . . 355
IAEA–CN–249–039 . . . . 189 IAEA–CN–249–115 . . . . 420 IAEA–CN–249–180 . . . . 401
IAEA–CN–249–040 . . . . 251 IAEA–CN–249–117 . . . . 221 IAEA–CN–249–182 . . . . 303
IAEA–CN–249–041 . . . . 304 IAEA–CN–249–118 . . . . 241 IAEA–CN–249–183 . . . . 157
IAEA–CN–249–042 . . . . 253 IAEA–CN–249–119 . . . . 405 IAEA–CN–249–184 . . . . . 92
IAEA–CN–249–044 . . . . 315 IAEA–CN–249–121 . . . . 307 IAEA–CN–249–186 . . . . 207
IAEA–CN–249–045 . . . . 354 IAEA–CN–249–122 . . . . 148 IAEA–CN–249–187 . . . . 347
IAEA–CN–249–047 . . . . 388 IAEA–CN–249–123 . . . . 436 IAEA–CN–249–188 . . . . 384
IAEA–CN–249–049 . . . . . 85 IAEA–CN–249–124 . . . . 404 IAEA–CN–249–189 . . . . 385
IAEA–CN–249–050 . . . . 327 IAEA–CN–249–126 . . . . 386 IAEA–CN–249–193 . . . . 300
IAEA–CN–249–051 . . . . . 98 IAEA–CN–249–127 . . . . 161 IAEA–CN–249–194 . . . . 286
IAEA–CN–249–053 . . . . 214 IAEA–CN–249–128 . . . . 237 IAEA–CN–249–195 . . . . 322
IAEA–CN–249–054 . . . . 149 IAEA–CN–249–132 . . . . 204 IAEA–CN–249–196 . . . . 438
IAEA–CN–249–055 . . . . 314 IAEA–CN–249–133 . . . . 363 IAEA–CN–249–197 . . . . 172
IAEA–CN–249–057 . . . . 219 IAEA–CN–249–134 . . . . 247 IAEA–CN–249–203 . . . . 422
IAEA–CN–249–058 . . . . 382 IAEA–CN–249–135 . . . . 252 IAEA–CN–249–206 . . . . 171
IAEA–CN–249–059 . . . . 181 IAEA–CN–249–136 . . . . 279 IAEA–CN–249–208 . . . . 413
IAEA–CN–249–060 . . . . 146 IAEA–CN–249–138 . . . . 415 IAEA–CN–249–210 . . . . 376
IAEA–CN–249–061 . . . . . 99 IAEA–CN–249–139 . . . . 373 IAEA–CN–249–212 . . . . 109
IAEA–CN–249–062 . . . . 267 IAEA–CN–249–140 . . . . 329 IAEA–CN–249–213 . . . . 130
IAEA–CN–249–065 . . . . 215 IAEA–CN–249–141 . . . . . 96 IAEA–CN–249–214 . . . . 399
IAEA–CN–249–066 . . . . 432 IAEA–CN–249–142 . . . . . 93 IAEA–CN–249–216 . . . . 439
449
ICARST–2017
IAEA–CN–249–217 . . . . 311 IAEA–CN–249–294 . . . . 383 IAEA–CN–249–369 . . . . 313
IAEA–CN–249–218 . . . . 372 IAEA–CN–249–295 . . . . 167 IAEA–CN–249–370 . . . . 105
IAEA–CN–249–219 . . . . 301 IAEA–CN–249–296 . . . . 266 IAEA–CN–249–372 . . . . 268
IAEA–CN–249–220 . . . . 183 IAEA–CN–249–297 . . . . 243 IAEA–CN–249–373 . . . . 184
IAEA–CN–249–221 . . . . 369 IAEA–CN–249–298 . . . . 358 IAEA–CN–249–376 . . . . 277
IAEA–CN–249–222 . . . . 350 IAEA–CN–249–300 . . . . 340 IAEA–CN–249–377 . . . . 324
IAEA–CN–249–223 . . . . 435 IAEA–CN–249–301 . . . . 362 IAEA–CN–249–378 . . . . 160
IAEA–CN–249–224 . . . . 156 IAEA–CN–249–302 . . . . 270 IAEA–CN–249–380 . . . . 150
IAEA–CN–249–225 . . . . 338 IAEA–CN–249–303 . . . . 142 IAEA–CN–249–381 . . . . 443
IAEA–CN–249–226 . . . . 339 IAEA–CN–249–304 . . . . 143 IAEA–CN–249–383 . . . . 239
IAEA–CN–249–227 . . . . 185 IAEA–CN–249–308 . . . . 225 IAEA–CN–249–384 . . . . 186
IAEA–CN–249–228 . . . . 163 IAEA–CN–249–311 . . . . 257 IAEA–CN–249–385 . . . . . 86
IAEA–CN–249–229 . . . . 107 IAEA–CN–249–314 . . . . 345 IAEA–CN–249–386 . . . . 295
IAEA–CN–249–230 . . . . 410 IAEA–CN–249–315 . . . . 320 IAEA–CN–249–387 . . . . 348
IAEA–CN–249–232 . . . . 191 IAEA–CN–249–316 . . . . 429 IAEA–CN–249–388 . . . . 111
IAEA–CN–249–234 . . . . 323 IAEA–CN–249–317 . . . . 310 IAEA–CN–249–390 . . . . 360
IAEA–CN–249–235 . . . . 389 IAEA–CN–249–319 . . . . 258 IAEA–CN–249–391 . . . . 282
IAEA–CN–249–236 . . . . 351 IAEA–CN–249–320 . . . . 246 IAEA–CN–249–392 . . . . 406
IAEA–CN–249–237 . . . . 379 IAEA–CN–249–321 . . . . 321 IAEA–CN–249–395 . . . . 120
IAEA–CN–249–238 . . . . 393 IAEA–CN–249–322 . . . . 129 IAEA–CN–249–398 . . . . 144
IAEA–CN–249–239 . . . . 343 IAEA–CN–249–323 . . . . 222 IAEA–CN–249–399 . . . . 193
IAEA–CN–249–240 . . . . 264 IAEA–CN–249–325 . . . . 155 IAEA–CN–249–400 . . . . 428
IAEA–CN–249–241 . . . . 190 IAEA–CN–249–327 . . . . 297 IAEA–CN–249–401 . . . . 387
IAEA–CN–249–243 . . . . 164 IAEA–CN–249–328 . . . . 195 IAEA–CN–249–402 . . . . 425
IAEA–CN–249–244 . . . . 272 IAEA–CN–249–329 . . . . 444 IAEA–CN–249–403 . . . . 187
IAEA–CN–249–248 . . . . 352 IAEA–CN–249–330 . . . . 140 IAEA–CN–249–404 . . . . 119
IAEA–CN–249–250 . . . . 280 IAEA–CN–249–331 . . . . 117 IAEA–CN–249–408 . . . . 170
IAEA–CN–249–252 . . . . 364 IAEA–CN–249–332 . . . . 390 IAEA–CN–249–409 . . . . 365
IAEA–CN–249–254 . . . . 402 IAEA–CN–249–336 . . . . 176 IAEA–CN–249–410 . . . . 192
IAEA–CN–249–255 . . . . 335 IAEA–CN–249–337 . . . . . 89 IAEA–CN–249–411 . . . . 234
IAEA–CN–249–256 . . . . 412 IAEA–CN–249–338 . . . . 431 IAEA–CN–249–412 . . . . 380
IAEA–CN–249–257 . . . . 370 IAEA–CN–249–339 . . . . 199 IAEA–CN–249–413 . . . . 408
IAEA–CN–249–258 . . . . . 97 IAEA–CN–249–341 . . . . 368 IAEA–CN–249–414 . . . . 298
IAEA–CN–249–259 . . . . 325 IAEA–CN–249–342 . . . . 230 IAEA–CN–249–415 . . . . 182
IAEA–CN–249–261 . . . . 381 IAEA–CN–249–343 . . . . 128 IAEA–CN–249–416 . . . . 430
IAEA–CN–249–263 . . . . 291 IAEA–CN–249–344 . . . . 391 IAEA–CN–249–417 . . . . 210
IAEA–CN–249–264 . . . . 147 IAEA–CN–249–345 . . . . 213 IAEA–CN–249–418 . . . . 154
IAEA–CN–249–269 . . . . 374 IAEA–CN–249–346 . . . . 121 IAEA–CN–249–419 . . . . 112
IAEA–CN–249–272 . . . . 400 IAEA–CN–249–347 . . . . 434 IAEA–CN–249–421 . . . . 169
IAEA–CN–249–273 . . . . 179 IAEA–CN–249–349 . . . . 125 IAEA–CN–249–422 . . . . . 82
IAEA–CN–249–274 . . . . 126 IAEA–CN–249–350 . . . . 259 IAEA–CN–249–424 . . . . 200
IAEA–CN–249–275 . . . . 316 IAEA–CN–249–352 . . . . 378 IAEA–CN–249–425 . . . . 174
IAEA–CN–249–277 . . . . 424 IAEA–CN–249–353 . . . . 293 IAEA–CN–249–426 . . . . 294
IAEA–CN–249–278 . . . . 417 IAEA–CN–249–355 . . . . 265 IAEA–CN–249–427 . . . . 276
IAEA–CN–249–279 . . . . 426 IAEA–CN–249–356 . . . . 256 IAEA–CN–249–428 . . . . 177
IAEA–CN–249–281 . . . . 166 IAEA–CN–249–357 . . . . 153 IAEA–CN–249–430 . . . . 284
IAEA–CN–249–282 . . . . 233 IAEA–CN–249–358 . . . . 309 IAEA–CN–249–431 . . . . 285
IAEA–CN–249–283 . . . . 240 IAEA–CN–249–360 . . . . 202 IAEA–CN–249–432 . . . . 133
IAEA–CN–249–284 . . . . 261 IAEA–CN–249–361 . . . . 427 IAEA–CN–249–433 . . . . 196
IAEA–CN–249–285 . . . . 353 IAEA–CN–249–362 . . . . 108 IAEA–CN–249–434 . . . . 289
IAEA–CN–249–287 . . . . 220 IAEA–CN–249–363 . . . . 346 IAEA–CN–249–435 . . . . 209
IAEA–CN–249–290 . . . . . 90 IAEA–CN–249–365 . . . . 278 IAEA–CN–249–436 . . . . 250
IAEA–CN–249–291 . . . . 113 IAEA–CN–249–367 . . . . 287 IAEA–CN–249–437 . . . . 226
IAEA–CN–249–293 . . . . 437 IAEA–CN–249–368 . . . . 178 IAEA–CN–249–438 . . . . 141
450
ICARST–2017
IAEA–CN–249–440 . . . . 123 IAEA–CN–249–446 . . . . 288 IAEA–CN–249–452 . . . . . 83
IAEA–CN–249–441 . . . . 248 IAEA–CN–249–447 . . . . 115 IAEA–CN–249–453 . . . . . 87
IAEA–CN–249–442 . . . . 114 IAEA–CN–249–448 . . . . . 84 IAEA–CN–249–454 . . . . 197
IAEA–CN–249–443 . . . . 100 IAEA–CN–249–449 . . . . 341 IAEA–CN–249–455 . . . . 254
IAEA–CN–249–444 . . . . 423 IAEA–CN–249–450 . . . . 127 IAEA–CN–249–457 . . . . . 80
IAEA–CN–249–445 . . . . 281 IAEA–CN–249–451 . . . . 198 IAEA–CN–249–458 . . . . 175
451
Contributor Index
— A — Antonio, P. L. . . . . . . . . . . . . . . . . . . .350, 428
Abad, L. V. . . . . . . . . . . . . . . . . . . . 16, 85, 385 Aoki, P. E. . . . . . . . . . . . . . . . . . . . . . . . . . . .254
Abaza, A. . . . . . . . . . . . . . . . . . . . . . . . 30, 297 Appiah, G. K. . . . . . . . . . . . . . . . . . . . . . . . 268
Abd El Slam, T. . . . . . . . . . . . . . . . . . . 24, 225 Aquino, D. . . . . . . . . . . . . . . 23, 49, 220, 294
Abd El-Rehim, H. A.. . . . . . . . . . . . .94, 375 Arahmane, H. . . . . . . . . . . . . . . . . . . . 47, 287
Abdelbari, A. O. A. . . . . . . . . . 33, 422, 438 Araújo, M. F. . . . . . . . . . . . . . . . . . . . . . . . . 370
Abdelgawad, S. . . . . . . . . . . . . . . . . . . 30, 298 Arjona, I. . . . . . . . . . . . . . . . . . . . . . . . . . . . 425
Abdelrehim, S. . . . . . . . . . . . . . . . . . . 41, 360 Artemiev, B. . . . . . . . . . . . . . 36, 46, 252, 279
Abdul Hamid, S. S. . . . . . . . . . . . . . . . . . 391 Artemyev, I. . . . . . . . . . . . . . . . . . . . . 252, 279
Abdullah, J. . . . . . . . . . 30, 40, 238, 271, 299 Asolekar, S. R. . . . . . . . . . . . . . . . . . . 267, 321
Abdullahi, A. S. . . . . . . . . . . . . . . . . . 49, 292 Aurigue, F. . . . . . . . . . . . . . . . . . . . . . . . . . . . 85
Acharya, P. . . . . . . . . . . . . . . . . . . . . . . . . . 348
Achilli, E. . . . . . . . . . . . . . . . . . . . . . . . . . . . 167 — B —
Adjerad, A. . . . . . . . . . . . . . . . . . . . . . . 30, 300 Baccaro, S. . . . . . . . . . . . . . . . . . . . . . 143, 302
Adu, P. S. . . . . . . . . . . . . . . . . . . . . . . .268, 273 Badita, E. . . . . . . . . . . . . . . . . . . . . . . . . . . . 364
Adu-Gyamfi, A. . . . . . . . . . . . . . . . . . 47, 177 Bahnarel, I. . . . . . . . . . . . . . . . . . . . . . . . . . 309
Adzaklo, S. Y. . . . . . . . . . . . . . . . . . . 268, 273 Bai, H. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 303
Affum, H. A. . . . . . . . . . . . 20, 204, 268, 273 Bailey, M. . . . . . . . . . . . . . . . . . . . . 23, 30, 120
Afroz, T. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 362 Bajpai, P. K. . . . . . . . . . . . . . . . . 207, 219, 388
Aguilera-Corrales, Y. . . . . . . . . . . . . 41, 361 Banoqitah, E. . . . . . . . . . . . . . . . . . . . . . . . 432Baricholo, P. . . . . . . . . . . . . . . . . . . . . . 49, 293
Ahmad Fadzil, M. F. . . . . . . . . . . . . . . . . 391 Barilla, J. . . . . . . . . . . . . . . . . . . . . . . . . 22, 116
Ahmad, F. . . . . . . . . . . . . . . . . . . . . . . . . . . 378 Barragán, M. . . . . . . . . . . . . . . . . . . . . . . . . 425
Aktar, J. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .362 Barrera Gonzalez, G. . . . . . . . . . . . . . . . . 342
Al-Bazzaz, H. . . . . . . . . . . . . . . 217, 218, 228 Bartilol, S. . . . . . . . . . . . . . . . . . . . . . . . . . . 277
Al-Dahhan, M.23, 217, 218, 227, 228, 232, Batchelor, B. . . . . . . . . . . . . . . . . . . . . 107, 163
235 Batista, J. G. D. S. . . . . . . . . . . . . . . . . . . . 170
Al-Saedi, J. K. J. . . . . . . . . . . . . . . . . . 33, 423 Belouadah, N. . . . . . . . . . . . . . . . . . . . . . . 230
Al-Sheikhly, M. . . . . . . . . . . . . . . . . . . 22, 112 Belyakov, O. . . . . . . . . . . . . . . . . . . . . . 25, 130
Alami, R.20, 26, 29, 33, 40, 46, 49, 202, 233, Ben Abdelouahed, H. 20, 27, 33, 197, 205,
261, 266, 272, 280, 282, 335, 424 238
Albino, C. . . . . . . . . . . . . . . . . . . . . . . . . . . 144 Ben Ouada, H. . . . . . . . . . . . . . . . . . 117, 390
Alcerreca, M. . . . . . . . . . . . . . . . . . . . . 37, 155 Benahmed, A. . . . . . . . . . . . . . . . . . . . . . . 424
Alexander, V. . . . . . . . . . . . 23, 217, 218, 228 BenMiloud, N. . . . . . . . . . . . . . . . . . . . . . . 340
Alias, M. S. . . . . . . . . . . . . . . . . . . . . . . . . . 394 Bensitel, A. . . . . . . . . . . . . . . . . . . . . . . . . . 282
Aljohani, M. . . . . . . . . . . . . . . . . . . . . 301, 311 Bergaoui, K. . . . . . . . . . . . . . . . . . . . . . 30, 304
Alkhansa, M. . . . . . . . . . . . . . . . . . . . . . . . 387 Bernardi, J. . . . . . . . . . . . . . . . . . . . . . . . . . 439
Alkhuraiji, T. . . . . . . . . . . . . . . . . . . . . . . . .326 Berne, P. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 246
Almahi, W. . . . . . . . . . . . . . . . . . . . . . . . . . 387 Betesho Babrud, R. . . . . . . . . . .30, 305, 306
Alonso, S. D. V. . . . . . . . . . . . . . . . . . . . . . 167 Bezsenyi, A. . . . . . . . . . . . . . . . . . . . . . . . . 164
Alves, L. C. . . . . . . . . . . . . . . . . . . . . . . . . . 370 Bezuglov, V. . . . . . . . . . . . . . . . . . . . . . . . . 135
Alzubair, O. M. E. . . . . . . . . . . . . . . . . . . . 422 Bhar, K. . . . . . . . . . . . . . . . . . . . . . . . . . 21, 211
Amano, Y. . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 Bhunia, H. . . . . . . . . . 43, 207, 219, 286, 388
Anessi, M. C. . . . . . . . . . . . . . . . 41, 355, 363 Bin Ahmad, M. . . . . . . . . . . . . . . . . . . . . . 172
452
ICARST–2017
Bireta, P. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 183 Chen, J. . . . . . . . . . . . . . . . . . . . . . . . . . 19, 101
Biswal, J. . . . . . . . . . . . . . . . . . . . . . . . . . . . 219 Chentouf, M. . . . . . . . . . . . . . . . . . . . 156, 338
Bjørn Tore, H. . . . . . . . . . . . . . . . . . . . . . . . 259 Cherkaoui El Moursli, R. . . . . . . . . . . . . 287
Bjørnstad, T. . . . . . . . . . . . . . 17, 47, 284, 285 Chinthaka, S. D. M. . . . . . . . . . . . . . . . . . 366
Bondar, Y. . . . . . . . . . . . . . . . . . . . . . . . 45, 171 Chmielewska-Śmietanko, D. 30, 308, 322
Bordei, N. . . . . . . . . . . . . . . . . . . . . . . . . . . 364 Chmielewski, A. G. . . . . . . 16, 80, 109, 441
Borjanović, V. . . . . . . . . . . . . . . . . . . . . . . . 400 Chu, L. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 106
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Hamzaoui, E. M. . . . . . . . . . . . . . . . . . . . . 287 Jovanović, D.. . . . . . . . . . . . . . . . . . . . . . . .381
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Marra Neto, A. . . . . . . . . . . . . . . . . . . . . . .254 — N —
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Ranković, D. . . . . . . . . . . . . . . . . . . . . . . . . 402 Said, I. A. . . . . . . . . . . . . . . . . . . . . . . . . . . . 235
Rao Damarla, H. . . . . . . . . . . . . . . . . . . . . 183 Saito M. de Barros, V. . . . . . . . . . . . . . . . 428
Rao, P. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 203 Salgado, F. . . . . . . . . . . . . . . . . . . . . . . 32, 346
458
ICARST–2017
Salifu, A. S. . . . . . . . . . . . . . . . . . . . . . . . . . 273 Sithole, P. . . . . . . . . . . . . . . . . . . . . . . . . . . . 293
Salih, A. . . . . . . . . . . . . . . . . . . . . 45, 172, 387 Smolinski, T. . . . . . . . . . . . . . . . . 34, 245, 441
Salimov, R. . . . . . . . . . . . . . . . . . . . . . . . . . 150 Soccio, M. . . . . . . . . . . . . . . . . . . . . . . . . . . 393
Salla Ferreira, M. . . . . . . . . . . . . . . . . 44, 408 Sohn, J.-Y. . . . . . . . . . . . . . . . . . . . . . . . . . . . 325
Salouti, M. . . . . . . . . . . . . . . . . . . . . . . . . . . 407 Soliman, E.-S. . . . . . . . . . . . . . . . . . . . . . . . 401
Salvador, P. A. V. . . . . . . . . . . . . . . . . . . . . 175 Solomon, H. . . . . . . . . . . . . . . . . . . . . . . . . 176
Salvan, C. . . . . . . . . . . . . . . . . . . . . . . . . . . . 144 Soltes, J. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 434
Samantray, J. S. . . . . . . . . . . . . 267, 321, 341 Somessari, S. L. . . . . . . . . . . . . . . . . . . . . . 175
Sampa, M. H. O. . . . . . . . . . . . . . . . . . . . . 175 Son, Y.-S. . . . . . . . . . . . . . . . . . . . . . . . . . . . 349
Sangal, V. K. . . . . . . . . . . . . . . . . . . . . . 20, 207 Sousa Carvalho, D. V. . . . . . . . . . . . . . . . 193
Santoro, N. . . . . . . . . . . . . . . . . . . . . . . . . . 363 Souza Santos, P. . . . . . . . . . . . . . . . . . . . . .354
Santoso, S. . . . . . . . . . . . . . . . . . . . . . . . . . . 442 Souza, D. . . . . . . . . . . . . . . . . . . . . . . . . 33, 350
Sarkar, M. . . . . . . . . . . . . . . . . . . . . . . . . . . 207 Souza, L. . . . . . . . . . . . . . . . . . . . . . . . . . . . 350
Sarma, K. S. S. . . . . . . . . . . . . . . . . . . . . . . 319 Spasojević, J. . . . . . . . . . . . . . . .381, 402, 412
Sayed, H. . . . . . . . . . . . . . . . . . . . . . . . . 44, 409 Sprenger, F. E. . . . . . . . . . . . . . . . . . . . . . . 175
Sbarcea, G. . . . . . . . . . . . . . . . . . . . . . . . . . 418 Staack, D. . . . . . . . . . . . . . . . . . . . . . . . 48, 183
Scarisoreanu, A. . . . . . . . . . . . . . . . . . . . . 364 Stancu, E. . . . . . . . . . . . . . . . . . . . . . . . . . . . 364
Schild, D. . . . . . . . . . . . . . . . . . . . . . . . . . . . 405 Steffens, D. . . . . . . . . . . . . . . . . . . . . . . . . . 380
Schmitz, F. . . . . . . . . . . . . . . . . . . . . . . 37, 154 Stein-Arild, T. . . . . . . . . . . . . . . . . . . . . . . . 259
Schoebel, M. . . . . . . . . . . . . . . . . . . . . . . . . 439 Stipanovic, A. . . . . . . . . . . . . . . . . . . . . . . . 184
Sebastian Calvo, C. . . . . . . . . . . . . . . 24, 226 Stoleru, E. . . . . . . . . . . . . . . . . . . . . . . . . . . . 93
Šegvić Klarić, M. . . . . . . . . . . . . . . . . 32, 347 Strzelec, A. . . . . . . . . . . . . . . . . . . . . . . . . . 183
Selambakkannu, S. . . . . . . . . . . . . . . . . . .102 Suárez-Antola, R. . . . . . . . . . . . . . . . . 22, 214
Senna, M. . . . . . . . . . . . . . . . . . . . . . . . . . . . 128 Sugiharto, S. . . . . . . . . . . . . .20, 34, 206, 442
Sereeter, L. . . . . . . . . . . . . . . . . . . . . . . 34, 440 Sultan, A. . . . . . . . . . . . . . . . . . . . 26, 227, 232
Setnescu, R. . . . . . . . . . . . . . . . . . . . . . . . . .384 Sun, Y. . . . . . . . . . . . . . . . . . . . . . . . . . . 21, 109
Shah, B. R. . . . . . . . . . . . . . . . . . . . . . . 32, 348 Sutapa, I. D. A. . . . . . . . . . . . . . . . . . . 35, 443
Shahid, A. . . . . . . . . . . . . . . . . . . . . . . . . . . 378 Suwanmala, P. . . . . . . . . . . . . . . . . . . . . . . 185
Shari, M. R. . . . . . . . . . . . . . . . . . . . . . . . . . 299 Székács, A. . . . . . . . . . . . . . . . . . . . . . . . . . 164
Sharma, V. K. . . . . . 207, 211, 286, 341, 410 — T —
Shayanfar, S. . . . . . . . . . . . . . . . . . . . . 44, 410 Taibouni, N. . . . . . . . . . . . . . . . . . . . . . . . . 230
Shehata, M. . . . . . . . . . . . . . . . . . . . . . . . . . 369 Tajau, R. . . . . . . . . . . . . . . . . . . . . . . . . 172, 391
Sheikh, N. . . . . . . . . . . . . . . . . . . . . . . . . . . 305 Takács, E. . . . . . . . . . . . 21, 38, 105, 164, 351
Shen, L. . . . . . . . . . . . . . . . . . . . . . . . 16, 35, 83 Takács, S. . . . . . . . . . . . . . . . . . . . . . . . . . . . 253
Sheoran, M. . . . . . . . . . . . . . . . . . . . . . . . . .219 Takriti, S. . . . . . . . . . . . . . . . . . . . . . . . . . . . 199
Shim, B. . . . . . . . . . . . . . . . . . . . . . . . . 162, 328 Tala-Eghil, R. . . . . . . . . . . . . . . . . . . . . . . . 329
Shin, J. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 325 Talcott, S. . . . . . . . . . . . . . . . . . . . . . . . . . . . 410
Shtarklev, E. . . . . . . . . . . . . . . . . . . . . . . . . 135 Talsmat, K. . . . . . . . . . . . . . . . . . . . . . . . . . 335
Shukri, N. A. . . . . . . . . . . . . 44, 92, 102, 411 Tartaro Bujak, I. . . . . . . . . 44, 334, 389, 413
Sidorov, A. . . . . . . . . . . . . . . . . . . . . . . . . . .135 Tegze, A. . . . . . . . . . . . . . . . . . . . . . . . . 33, 351
Silva, C. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 380 Telleria, D. . . . . . . . . . . . . . . . . . . . . . . 18, 198
Silva, L. G. A. . . . . . . . . . . . . . . . . . . . . . . . 175 Terrier, P. . . . . . . . . . . . . . . . . . . . . . . . . . . . 213
Simr, P. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 116 Thereska, J. . . . . . . . . . 20, 39, 197, 205, 263
Singh, D. . . . . . . . . . . . . . . . . . . . . . . . . . . . 286 Thoma, M. . . . . . . . . . . . . . . . . . . . . . . . . . . 149
Siplak, D. . . . . . . . . . . . . . . . . . . . . . . . . . . . 316 Thomaz, R. . . . . . . . . . . . . . . . . . . . . . . . . . 396
Siri, M. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 167 Thomé, Z. . . . . . . . . . . . . . . . . . 310, 320, 429
459
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Thompson, T. . . . . . . . . . . . . . . . . . . . . . . . 183 Wang, H. . . . . . . . . . . . . . . . . . . . . . . . . . . . 187
Tickner, J. . . . . . . . . . . . . . . . . . . . 29, 237, 247 Wang, J. . . . . . . . . . . . . . . . . . . . . . . . . . 21, 106
Ting, T. M. . . . . . . . . . . . . . . . . . . . . . . 44, 414 Wang, L. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 163
Tissot, C. . . . . . . . . . . . . . . . . . . . . . . . . . . . .247 Wang, M. . . . . . . . . . . . . . . . . . . . . . . . . 44, 415
Tiwari, P. . . . . . . . . . . . . . . . . . . . . . . . . . . . 264 Wang, Z. . . . . . . . . . . . . . . . . . . . . . . . . 97, 382
Tkachenko, V. . . . . . . . . . . . . . . . . . . . . . . .135 Warnakulasuriya, T. . . . . . . . . . . . . . . . . .444
Toukan, A. . . . . . . . . . . . . . . . . . . 24, 217, 228 Weerakkody Appuhamillage, T. . 35, 444
Trabelsi, M. H. . . . . . . . . . . . . . . . . . . 33, 352 Weerasooriya, R. . . . . . . . . . . . . . . . . . . . . 405
Trabelsi, Z. . . . . . . . . . . . . . . . . . . . . . . . . . .352 Weidauer, A. . . . . . . . . 33, 35, 149, 151, 356
Tran Thanh, M. . . . . . . . . . . . . . . . . . . . . . 221 Wibisono, W. . . . . . . . . . . . . . . . . . . . . . . . 442
Tran Tri, H. . . . . . . . . . . . . . . . . . . . . . . . . . 189 Wickremasinghe, R. . . . . . . . . . . . . . . . . .444
Tran, Q.-K. . . . . . . . . . . . . . . . . . . 28, 142, 144 Wiens, R. . . . . . . . . . . . . . . . . . . . . . . . . 27, 133
Trautmann, C. . . . . . . . . . . . . . . . . . . . . . . 396 Williams, S. . . . . . . . . . . . . . . . . . . . . . . . . . 444
Tripathi, A. . . . . . . . . . . . . . . . . . . . . . . 33, 353
Tuan Abdullah, T. A. . . . . . . . . . . . . . . . . 102 Wishart, J. . . . . . . . . . . . . . . . . . . . . . . . . 16, 86Wojnárovits, L. . . . . . . . . . . 22, 41, 111, 164
— U — Wojtowicz, P. . . . . . . . . . . . . . . . . . . . . . . . .441
Ud Din, G. . . . . . . . . . . . . . . 37, 39, 256, 265 Wu, G. . . . . . . . . . . . . . . . . . . . . . . . . . . 48, 187
Ulański, P. . . . . . . . . . . . . . . . . 16, 45, 82, 182 Wu, M.-H. . . . . . . . . . . . . . . . . . . . . . . . 38, 161
Ulbert, S. . . . . . . . . . . . . . . . . . . . . . . . . . . . 149 Wu, Q. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 331
Upadhyay, R. K. . . . . . . . . . . . . . . . . 190, 264
— V — — X —
Vancea, C. . . . . . . . . . . . . . . . . . . . . . . . . . . 364 Xia, X. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 122
Varca, G. H. C. . . . . . . . . . . 42, 45, 170, 380 Xiang, X. . . . . . . . . . . . . . . . . . . . . . . . . . . . .239
Varshney, L. . . . . . . . . . . . . . . . . . . . . . . . . 388 Xu, L. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 187
Vasile, C. . . . . . . . . . . . . . . . . . . . . . . . . . 18, 93
Vasileiadis, A. . . . . . . . . . . . . . . . . . . . . . . 215
Vasquez, P. . . . . 16, 28, 33, 87, 99, 139, 354
Velciu, G. . . . . . . . . . . . . . . . . . . . . . . . . . . . 418 — Y —
Velo, A. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 193 Yadav, A. . . . . . . . . . . . . . . . . . . . . . . . . . . . 192
Venkatesh, M. . . . . . . . . . . . . . . . . . . . . . . . .49 Yamato, M. E. . . . . . . . . . . . . . . . . . . . . . . . 428
Vianna Bandeira, J. . . . . . . . . . . . 21, 40, 212 Yamoah, S. . . . . . . . . . . . . . . . . . . . . . . . . . . 204
Villani, D. . . . . . . . . . . . . . . . . . . . . . . . . . . .427 Yang, D. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16
Vinnett, L. . . . . . . . . . . . . . . . . . . . . . . . . . . 244 Yang, J. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 157
Vlasov, A. . . . . . . . . . . . . . . . . . . . . . . . . . . . 135 Yang, Y. . . . . . . . . . . . . . . . . . . . . . . . . . 48, 288
Vogt, M. V. . . . . . . . . . . . . . . . . . . . . . . 33, 355 Yelgaonkar, V. . . . . . . . . . . . . . . . . . . . 20, 203
Voronin, L. . . . . . . . . . . . . . . . . . . . . . . . . . 135 Yin, Y. . . . . . . . . . . . . . . . . . . . . . . . . . . . 44, 416
Vulic, A. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 334 Yordanov, N. . . . . . . . . . . . . . . . . . . . . . . . . 327
Yousif, A. . . . . . . . . . . . . . . . . . . . . . . . . . . . 387
— W — Yu, G. . . . . . . . . . . . . . . . . . . . . . . . . . . . 37, 157
Wach, R. . . . . . . . . . . . . . . . . . . . . . . . . 48, 182 Yu, M. . . . . . . . . . . . . . . . . . . . . . . . . . . . 97, 382
Waduge, V. . . . . . . . . . . . . . . . . . . . . . . . . . 444 Yu, S. 31, 32, 38, 42, 44, 162, 325, 328, 349,
Wafaa, B. . . . . . . . . . . . . . . . . . . . . . . . . . . . 345 379, 417
Wahit, M. U. . . . . . . . . . . . . . . . . . . . . . . . . 411 Yun, J.-M. . . . . . . . . . . . . . . . . . . . . . . 379, 417
Wan Kamal, W. H. B. . . . . . . . . . . . . . . . . 391
Wan Yunus, W. M. Z. . . . . . . . . . . . . . . . 172
460
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— Z — Zhang, B. . . . . . . . . . . . . . . . . . . . . . . . . . . . 382
Zaharescu, T. . . . . . . . . . . . . 44, 93, 384, 418 Zhang, J. . . . . . . . . . . . . . . . . . . . . . . . . . . . .122
Zahoor, R. . . . . . . . . . . . . . . . . . . . . . . . . . . 378 Zhang, L. . . . . . . . . . . . . . . . . . . . . . . . . . . . 157
Zaman, M. B. U. . . . . . . . . . . . . . . . . . . . . 256 Zhang, Y. . . . . . . . . . . . 24, 35, 122, 146, 239
Zaouak, A. . . . . . . . . . . . . . . 33, 45, 357, 419
Zatko, B. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 406 Zhao, X. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 239
Zeng, X. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 420 Zhu, Z. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 157
Zeng, Z. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 157 Zimek, Z. . . . . . . . . . . . . . . . . . . . . . . . 33, 358
Zhai, M. . . . . . . . . . . . . . . . . . . . . . . . . . . 19, 96 Zong, C. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 237
461
ICARST–2017 Relevant IAEA publications
IAEA Publications
All IAEA publications may be ordered from the Sales and Promotion Unit,
International Atomic Energy Agency,
P.O. Box 100, A-1400 Vienna, Austria
Fax: +43 1 2600-29302
sales.publications@iaea.org
www.iaea.org/Publications/index.html
IAEA Publications Related to this Conference
2016 The Radiation Chemistry of Polysaccharides
STI/PUB/1731; ISBN: 978-92-0-101516-7
2016 Radiation Technology for Cleaner Products and Processes
IAEA-TECDOC-1786; ISBN: 978-92-0-101016-2
2015 Nanoscale Radiation Engineering of Advanced Materials for Potential
Biomedical Applications
STI/PUB/1684; ISBN: 978-92-0-101815-1
2015 Utilization of Accelerator Based Real Time Methods in Investigation of
Materials with High Technological Importance
STI/PUB/1649; ISBN: 978-92-0-102314-8
2015 Radiation Curing of Composites for Enhancing Their Features and Utility in
Health Care and Industry
IAEA-TECDOC-1764; ISBN: 978-92-0-103815-9
2015 Use of Radiotracers to Study Surface Water Processes
IAEA-TECDOC 1760; ISBN: 978-92-0-100415-4
2014 Radiation Processed Materials in Products from Polymers for Agricultural
Applications
IAEA-TECDOC-1745; ISBN: 978-92-0-106414-1
2014 Radiotracer and Sealed Sources Applications in Sediment Transport Studies
IAEA Training course series № 59
2013 Guidelines for Development, Validation and Routine Control of Industrial
Radiation Processes
IAEA Radiation Technology Series № 4, STI/PUB/1581; ISBN: 978-92-0-135710-6
2013 Design, Development and Optimization of a Low Cost System for Digital
Industrial Radiology
IAEA Radiation Technology Reports № 2, STI/PUB/1561; ISBN: 978-92-0-129310-7
2013 Radiotracer Generators for Industrial Applications
IAEA Radiation Technology Series № 5, STI/PUB/1579; ISBN: 978-92-0-135410-5
462
Relevant IAEA publications ICARST–2017
2012 Development of Novel Adsorbents and Membranes by Radiation Induced
Grafting for Selective Separation in Environmental and Industrial Applications
IAEA Radiation Technology Reports № 3 STI/PUB/1572; ISBN: 978-92-0-134010-8
2012 Neutron Generators for Analytical Purposes
IAEA Radiation Technology Reports № 1 STI/PUB/1535; ISBN: 978-92-0-125110-7
2012 Application of Radiotracer Techniques for Interwell Studies
IAEA Radiation Technology Series № 3 STI/PUB/1539; ISBN: 978-92-0-125610-2
2011 Nuclear Techniques for Cultural Heritage Research
IAEA Radiation Technology Series № 2 STI/PUB/1501; ISBN: 978-92-0-114510-9
2011 Use of Mathematical Modelling in Electron Beam Processing: A Guidebook
IAEA Radiation Technology Series № 1 STI/PUB/1474; ISBN: 978-92-0-112010-6
2011 Radiotracer Applications in Wastewater Treatment Plants
IAEA Training course series № 49
2009 Leak Detection in Heat Exchangers and Underground Pipelines Using
Radiotracers
IAEA Training course series № 38
2008 Radiotracer Residence Time Distribution Method for Industrial and
Environmental Applications
IAEA Training course series № 31
463
ICARST–2017 IAEAMeetings
Participation in an IAEA Scientific Meeting
Governments of Member States and those organizations whose activities are relevant to
the meeting subject matter are invited to designate participants in the IAEA scientific
conferences and symposia. In addition, the IAEA itself may invite a limited number of
scientists as invited speakers. Only participants designated or invited in this way are entitled
to present papers and take part in the discussions.
Representatives of the press, radio, television or other information media and members of
the public, the latter as “observers”, may also be authorized to attend, but without the right
to take part in the proceedings.
Scientists interested in participating in any of the IAEAmeetings should request information
from the Government authorities of their own countries, in most cases the Ministry of
Foreign Affairs or national atomic energy authority.
Upcoming IAEAMeetings
For complete information on forthcoming scientific meetings, please consult the IAEA
conference web site: http://www.iaea.org/meetings.
2017, 22–26 May 3rd FAO/IAEA International Conference on Area-wide
Vienna, Austria Management of Insect Pests: Integrating the Sterile Insect and
Related Nuclear and Other Techniques
2017, 30 May–1 June International Conference on the IAEA Technical Cooperation
Vienna, Austria Programme: Sixty Years and Beyond - Contributing to
Development
2017, 6–9 June International Conference on Topical Issues in Nuclear
Vienna, Austria Installation Safety: Safety Demonstration of Advanced Water
Cooled NPPs
2017, 20–23 June International Conference on Advances in Radiation Oncology
Vienna, Austria (ICARO2)
2017, 26–29 June International Conference on Fast Reactors and Related Fuel
Yekaterinburg, Russian Fed. Cycles (FR17)
2017, 19–20 September Scientific Forum: Nuclear Technology for Human Health:
Vienna, Austria Prevention, Diagnosis and Treatment
2017, 23–27 October Fourth International Conference on Nuclear Power Plant Life
Lyon, France Management (PLiM)
2017, 30 Oct.– 1 Nov. International Ministerial Conference on Nuclear Power in the
Abu Dhabi, UAE 21st Century
2017, 13–17 November International Conference on Physical Protection of Nuclear
Vienna, Austria Material and Nuclear Facilities
2017, 11–15 December International Conference on Radiation Protection in Medicine:
Vienna, Austria Achieving Change in Practice
464
IAEAMeetings ICARST–2017
2018, 28–31 May Third International Conference on Human Resource
Gyeongju, Rep. of Korea Development for Introducing and Expanding Nuclear Power
Programmes: Meeting Challenges to Ensure the Future
Nuclear Workforce Capability
2018, 25–29 June International Symposium on Uranium Raw Material for
Vienna, Austria Nuclear Fuel Cycle: Exploration, Mining, Production, Supply
and Demand, Economics and Environmental Issues
(URAM-2018)
2018, 6–10 August International Symposium on Plant Mutation Breeding and
Vienna, Austria Biotechnology
2018, 1–5 October International Symposium on Communicating Nuclear and
Vienna, Austria Radiological Emergencies to the Public
2018, 15–19 October International Conference on Challenges Faced by Technical
Brussels, Belgium and Scientific Support Organizations (TSOs) in Enhancing
Nuclear Safety and Security
2018, 22–27 October 27th IAEA Fusion Energy Conference (FEC–2018)
Ahmedabad, India
2018, 5–9 November Symposium on International Safeguards
Vienna, Austria
2018, 3–7 December International Conference on Global Radioactive Material
Vienna, Austria Security Governance: Prevention and Detection in Action
2018, To be Decided Ministerial Conference on Nuclear Science, Technology and
Vienna, Austria Applications for Peaceful Uses
2018, To be Decided International Symposium on Understanding the Double
Vienna, Austria Burden of Malnutrition for Effective Interventions
2019, To be Decided International Symposium on Trends in Radiopharmaceuticals
Vienna, Austria
465