ference onon Re C se International Atomic Energy Agency IAEA-CN-156 P.O. Box 100 Wagramer Strasse 5 Sydney A–1400 Vienna, Austria Ma 5–9 November 2007n tili Tel: +43 1 2600 0 agem tive U Fax: +43 1 2600 7 ent and Effec offi cial.mail@iaea.org PROGRAMME Organized by the International Atomic Energy Agency (IAEA) Hosted by the Government of Australia through the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) 07-30891-CN156-Sydney-prog1.indd 1 2007-09-06 14:55:02 International zation h Reactorsc ar e Saf NOTES IAEA Conference Secretariat: Scientific Secretaries: H. Abou Yehia P. Adelfang S. Paranjpe Conference Coordination: K. Morrison C. Coolbaugh Administrative Support: E. Bosch Local Coordination: M. Partridge Australian Radiation Protection and Nuclear Safety Agency Location of the Conference: Four Points by Sheraton Hotel Darling Harbour 161 Sussex Street Sydney NSW 2000 Tel: (61) (2) 9290 4000 Working Language: English Resolutions: No resolutions may be submitted for consideration on any subject; no votes will be taken. 36 TFOIMRTEHTCAOBMLINEG SCIENTIFIC MEETINGS SCHEDULED BY 13:30-15:10 Session 8 NOTES THE IAEA Specific Utilization Applications Monday, 5 November 2007 15:10-16:10 Poster Session with refreshments 2007 08:30 Registration 16:10-17:30 Session 9 International Symposium on Clinical PET and Molecular Medicine Decommissioning and Waste Management 10-14 November, Bangkok, Thailand 09:30-10:30 Session 1 International ConfeWreenlccoem oen &Ill iOcipt eNnuinclge aArd Tdrraefsfisceksin g: Thursday, 8 November 2007 C10o:l3le0c-t1iv0e:4 E5x pe rienCcoeff eaen dB trheea kW ay Forward 19-22 November, Edinburgh, UK 08:30-10:00 Session 7(Part II) 10:45-12:15 Session 2 10:00-10:30 Coffee Break Experience with the Code of Conduct on the 2008 Safety of Research Reactors 10:30-12:00 Session 10 12:15-13:30 Lunch Break International Conference on Topical Issues in Nuclear Installation Core Safety and Utilization Parameters S13afety, 12:00-13:20 Lunch Break :30-15:10 Session 3 Ensuring Safety for Sustainable Nuclear Development Sustainable Utilization and Strategies Mumbai, India 13:20-15:20 Session 11 15:10-15:40 Coffee Break Programmes for the Minimization of the Use of International Symposium on Induced Mutations in Plants HEU 1125-:4105- A17u:g0u0s t, V ienSneas,s Aiouns 3tr icao n’t 15:20-16:20 Poster Session with refreshments 19:00 Conference Dinner nd 22 IAEA Fusion Energy Conference 16:20-17:40 Session 12 13-18 October, Geneva, Switzerland New Research Reactor Projects Tuesday, 6 November 2007 International Conference on Nuclear Security: Global Directions f0o8r: 3th0e- 1F0u:1tu0r e Session 4(Part I) Friday, 9 November 2007 December, ViennaS, aAfuestytr Mia anagement and Operational Safety 10:10-10:30 Coffee Break 08:30-09:45 Session 13 For information on forthcoming scientific meetings, Panel Discussion p1l0e:a3s0e-1 c2o:0n0su lt t heS IAesEsAio wn e4b( Psaitret: Ih) tctpo:n//’tw ww.iaea.org/ 09:45-10:30 Coffee Break 12:00-13:30 Lunch Break 10:30-11:00 Session 14 13:30-15:10 Session 4(Part II) Concluding Remarks and Closing 15:10-16:10 Poster Session with refreshments 11:00 Depart for Technical Tour Return to Sydney 16:10-17:30 Session 5 approx. 18:00 Fast Flux Research Reactors Wednesday, 7 November 2007 08:30-10:00 Session 6 Networking for Research Reactor Utilization 10:00-10:30 Coffee Break 10:30-12:00 Session 7(Part I) Regulatory Aspects and Experience with Current Research Reactor Issues Including Safety Aspects of Core Conversion 12:00-13:30 Lunch Break 234 353 SDOUCNUDMAEYNT, 4 NOVEMBER 2007 DOCUMENT NUMBER TITLE YEAR NUMBER TITLE YEAR 16:00–19:00 Registration No. SF-1 EUROPEAN ATOMIC ENERGY 2006 TRS 446 Decommissioning of Research 2006 WeClcOoMmMeU RNeIcTeYp, tFioOnO D AND Reactors: Evolution, State of the Art, AGRICULTURE ORGANIZATION OF Open Issues THE UNITED NATIONS, INTERNATIONAL ATOMIC ENERGY TRS 455 Utilization Related Design Features of 2007 AGENCY, INTERNATIONAL LABOUR Research Reactors: A Compendium ORGANIZATION, INTERNATIONAL MONDAY, 5 NMOAVREITMIMBEE ORR G20A0N7IZ ATION, OECD Proceedings Research Reactor Utilization, Safety 2005 NUCLEAR ENERGY AGENCY, PAN Series Decommissioning, Fuel and Waste 08:30 ReAgMisEtrRaItCioAnN HEALTH ORGANIZATION, Management, Proceedings of an UNITED NATIONS ENVIRONMENT International Conference held in PROGRAMME, WORLD HEALTH Santiago, Chile, 10-14 November 2003 09:30–10:30 SESSION 1: WeOlcRoGmAeN &IZ AOTpIeOnNin, gF uAndddarmesesnetasl :S afety Miscellaneous INTERNATIONAL ATOMIC ENERGY 2004 Principles: Safety Fundamentals AGENCY, The Code of Conduct on the Representative of Australia Safety of Research Reactors Representative of the IAEA IAEA-TECDOCs 10:30–10:45 Coffee Break 792 INTERNATIONAL ATOMIC ENERGY 1995 10:45–12:15 SEASGSEIONNC Y2:, Management of Research ExRpearicetnocr eA gweiitnhg t he Code of Conduct on the Safety of Research Reactors 1212 Strategic Planning for Research 2001 ChRaeirapcetorsrson: L. Keen, Canada Co-Chairperson: J. Loy, Australia 1273 Decommissioning Techniques for 2002 No of Paper Research Reactors Designating Member Time IAEA-CN-156- Name State/Organization (min) Title of Paper 1374 Development Status of Metallic, 2003 S-1/OR J. Loy Australia 30 Where to with the Code of Conduct on the Safety of Dispersion and Non-oxide Advanced Research Reactors (Invited) and Alternative Fuels for Power and S-69/OR ReHs. eAabrcohu R Yeeahcitao rs IAEA 20 Feedback from the Regional Meetings on the Application of the Code of Conduct and Updating of the 1387 INTERNATIONAL ATOMIC ENERGY 2004 IAEA Programme on Research Reactors Safety AGENCY, Safety Considerations for S-3/OR ReAs. eSaarcpho zRhenaicktoovrs in ExRtuesnsdieadn Federation 20 Effectiveness of Safety Regulation at Russian Research Reactors in Compliance with International Practice Shutdown S-4/OR S. Tozser Hungary 20 Some Operational Aspects of BRR's Management 1508 Spent Fuel Management Options for 2006 System with Respect to the Code of Conduct Research Reactors in Latin America 12:15–13:30 Lunch Break Technical Report Series TRS 418 Corrosion of Research Reactor 2003 Aluminium Clad spent Fuel in Water TRS 443 Understanding and Managing Ageing of 2006 Material in Spent Fuel Storage Facilities 432 335 PARTICIPATION IN IAEA SCIENTIFIC MEETINGS MONDAY, 5 NOVEMBER 2007 DOCUMENT Governments of Member States and those organizations whose NUMBER TITLE YEAR 1a3ct:i3v0it–ie1s7 a:0re0 releSvEaSnSt ItOo Nth 3e: meeting subject matter are invited to designate partiSciupsatnatisn abinl e UIAtEiliAz atisocnie anntifdic S tcraotnefegriensc es and No. SF-1 EUROPEAN ATOMIC ENERGY 2006 symposia. In addition, the IAEA itself may invite a limited number COMMUNITY, FOOD AND of scientists as Cinhviateirdp esrpseoank:e rs. OR.nNly. Spaaxrteicnipaa, nBtsra dzeils ignated or AGRICULTURE ORGANIZATION OF invited in this waCyo a-Creh aeinrtpitelerds oton :p Sr.eKs.e Pnat rpaanpjepres, aIAnEd Ata ke part in THE UNITED NATIONS, the discussions. INTERNATIONAL ATOMIC ENERGY No of Paper Name Designating Member Time IAEA-CN-156- Title of P AapGeEr NCY, INTERNATIONAL LABOUR Representatives of the press, radio, Sttaetlee/vOisrigoann izoart iono ther (min) ORGANIZATION, INTERNATIONAL iUnf-o1r1m/OatRio n media San.Ld. Cmheampbloetr s of theI npduiab lic, the latter as 30 UtilizationM PArRoIgTrIaMmEm OeRs GFoArN LIoZwA TAIOndN M, OedEiCumD Flux “observers”, may also be authorized to attend, but without the ResearchN RUeCaLcEtoArRs ENERGY AGENCY, PAN right to take part in the proceedings. AMERICAN HEALTH ORGANIZATION, F-3/OR L. Ramanathan Brazil 20 A CorrosUioNn IMTEoDni tNorAinTgIO PNroSg EraNmVmIReO foNrM REeNseTa rch Scientists interested in participating in any of the IAEA meetings Reactor Spent Fuel Basins PROGRAMME, WORLD HEALTH lUis-te4d0 /OinR this prograRm.Nm. eS asxheonuald requestB irnafzoirl mation from the 20 The IEA-OR1R GRAesNeIZarAcThI ORNea, cFtuonr:d 5a0m YeEntAaRl Sa ofef tOy perating governmental authorities of their own countries, in most cases ExperienPceri nacnipdl eUst:il iSzatfieotny fFour nRdeasmeeanrctahl,s T eaching and the Ministry of Foreign Affairs or national atomic energy authority. Radioisotopes Production U-43/OR B.S. Yuldashev Uzbekistan I2A0E A-TECTDhOe CUstilization of 10 MW Research Reactor in Tashkent PUBLICATIONS 1P5ro:1c0e–e1d5i:n4g0s Coffee Break 792 INTERNATIONAL ATOMIC ENERGY 1995 AGENCY, Management of Research TUh-e1 3p/rOoRce edings of Bth.eJ .cBo.n Nfeyraernkcoe will be Gphuabnlisah ed by the IAEA 20 The 30 kWRe Racetsoer aArgche inRge actor Facility in Ghana: Past, in unedited form as a CD-Rom and will be sent to all participants Present and Future Programmes 1212 Strategic Planning for Research 2001 aUft-e1r8 t/hOeR m eeting. W.H.A. Beere Norway 20 The HaldRene aRcetoarcstor Project: Experience gained in International Research Orders U-35/OR M.I. Itoh Japan 12207 3 The UtilizDaeticoonm omf Risessioenairncgh TReecahcntioqruse asn fdo rr elated 2002 IAEA publications may be ordered at the Conference Desk or Facilities Rfoers tehaer cShu Rppeoarctitnogrs o f Innovative Power directly from the Sales and Promotion Unit Reactor and Related Fuel Cycle International Atomic Energy Agency, P.O. Box 100 1374 Development Status of Metallic, 2003 1U4-090/O VRie nna, AustriaR . Rosa Italy 20 RACE-T DEixsppeerrismioenn taanl dA cNtoivnit-ioexsi d- eA nA dOvvaenrcveiedw of the Fax: (+43 1) 2600-29302 Subcritical Measurements Preliminary to the and Alternative Fuels for Power and Email: sales.publications@iaea.org Accelerator Coupling Experiment Research Reactors Internet: http://www.iaea.org/books 19:00 Conference Dinner 1387 INTERNATIONAL ATOMIC ENERGY 2004 AGENCY, Safety Considerations for Research Reactors in Extended Shutdown 1508 Spent Fuel Management Options for 2006 Research Reactors in Latin America Technical Report Series TRS 418 Corrosion of Research Reactor 2003 Aluminium Clad spent Fuel in Water TRS 443 Understanding and Managing Ageing of 2006 Material in Spent Fuel Storage Facilities 630 317 TNUo oEf SPDapAerY , 6 NOVEMBER 2007 Designating Member IAEA-CN-156- Name State/Organization Title of Paper 08:30–12:00 SESSION 4(Part I): U-50/PO SafeSty. NMilasnuawgaenmkeonsti ta nd TOhpaeilraantido nal Safety Implementation of TRR-1/M1 for Thailand’s Nuclear Engineering Programme Chairperson: J. Repussard, France Co-Chairperson: C. Maloney, Australia PNos otef rPsa:p er FNuaeml e Designating Member Time IAEA-CN-156- State/Organization (min) Title of Paper S-5/OR M.H. Voth USA 20 Improvements in the Management of Safety in No of Paper Name Designating Member IAEA-CN-156- State/Organization Title of Pa Rpesr earch Reactor Operation through Appropriate Application of Selected Power Reactor Good Practices SF--44/1P/OOR JG.. JB.o Sotgoarra rd NAuesthtrearlliaan ds C20o nvertinSg aHfeIFtyA MR aton aLgoewm Eennrt icaht eNdR UGr-aPneiuttmen F uel SF--65/2P/OOR DS.. KS.a Srkhaurk la IAnudsiatr alia T2h0e ReguSlaatfoertyy RMoalen aogf ethmee Antu astnrda liEafnfe Rctaivdeia Utiotinliz Partoiotne cotifo Inn dainadn Nuclear SRaefesteya Arcghe nRcayc itno rrse lAaPtioSnA tRoA S, pCeInRt UFSu eal nadr isDinHgR fUroVmA Research Reactors in Australia S-45/OR M. Latif Pakistan 20 Ageing Management of Pakistan Research Reactor-1 F-7/PO J.A. Sarta Fuentes Colombia Design an(dP AcoRnRs-t1ru) ction of a Decay Pool at IAN-R1 Research Reactor S-40/OR G. Bignan France 20 The Safety Reassessment of Research Reactors in DE-1/PO J. Kaulard Germany Safety AsFserasnscmeent for Decommissioning of Research Reactors – International Project on Evaluation and Demonstration of Safety S. Thierfeldt during Decommissioning of Nuclear Facilities (DeSa) 10:10–10:30 Coff(epere Bsreenatekd by) WM-4/PO A. Savidou Greece Further Development in Characterization of Radioactive Waste S-50/OR J. Repussard France D30ru ms byC Noomnp Dateibstilriutyc toivf eS Gafaemtym anad S Specturroitmy etry at GRR-1 FS--12/5P/O R MA..C C. iDocr agnoelsiciu Romania A2l0-C lad SpOepnetr Natuiocnleaal rS Fauf etly C Eoxrproesrieonc Set uadt i1e4s MatW M aTgRuIrGeAle Site, Romania Research Reactor from INR Pitesti, Romania FS--23/4P/O R AM.. Persšiic Selorvbeian ia V2I0N CA SitLeju Pbrlejapnaar aTtRioInG fAo rM SApRenKt IFI:u 4e0l SYheiaprms eonf tS uccessful Operation WM-5/PO Dung Tran Vietnam Experimental Study of Systematic Errors of Gamma for Assay of S-39/OR S. Nitiswati Indonesia R20a dioactivAeg eWinags tMe aDnraugmesm ent Programme of Kartini Reactor for Safe Operation 12:00–13:30 Lunch Break 828 29 TPoUsEteSrsD: AY, 6 NOUVtilEizaMtiBonE R 2007 13:30–15:10 SESSION 4 (Part II): No of Paper Safety Management and DOepseirgantaiotinga lM Seamfebtye r IAEA-CN-156- Name State/Organization Title of Paper Chairperson: J. Boogaard, Netherlands U-54/PO Co-CMh. aHirapqeures on: A. SapozBhannigkloadve, sRhu ssian Operating Experience Utilization Programmes of the BAEC 3 MW Federation TRIGA Mark-II Research Reactor in Bangladesh U-55/PO S. Abdul Latif Bangladesh Studies on Environmental Pollution in Bangladesh Using Reactor No of Paper Name Designating Member BTaimse d NeTuittrleo no fA Pcativpaetri on Analysis Technique IAEA-CN-156- State/Organization (min) U-8/PO R. Pugliesi Brazil Improvement on Sensitivity for the Track - Etch Neutron S-51/OR J. Couturier France R20a diograpPheyr iodic Safety Review Management for French Research Reactors - Technical Support Organization U-10/PO DA. RSoivaer e(psr eLseeanl ted Brazil New Perspectives for the TRIGA IPR-R1 Research Reactor by) Approach U-15/PO C.B.R. Parente Brazil First Experiments in the IPEN-CNEN/SP PSD Neutron Powder S-57/OR A.S. Vieira Neto Brazil D20if fractomEextpeer rience of IPEN-CNEN/SP in the Execution of the First Phase of the Safety Culture Enhancement U-45/PO K. Ilieva Bulgaria Future UtPilirzoagtiroanm omf eth aet RIEeAse-Ra1rc Bh rRazeialicatno rR IeRsTe ainr cSho Rfiae aacftteorr its Reconstruction S-58/OR J.-S. Wu Korea, Rep. of 20 Development of Safety Performance Indicators for U-38/PO M. Marek Czech Republic UtilizationH oAf NthAeR LOVR-15 Research Reactor at Rež US--4496//POOR SK.. MMaartgejekaan u CRzoemcahn Riae public U20ti lizationE omf ethrgee VnRcy-1 I nTtrearivneinngti oRne Palcatno rf o r 14 MW TRIGA - Pitesti U-28/PO I.H. Auterinen Finland The 250 kRWe sFeiaRr c1h T RReIGacAto Rr esearch Reactor - International Role i n Boron N eutron Capture Therapy (BNCT) and Regional Role in Isotope Production, Education and Training 1U5-:5160/P–1O6 :10 PostTe.rM S. eSsoseinotno (nSoa fety) wInitdho nreefsrieas hments 125 Feasibility Study of I Brachytherapy in Indonesia U-17/PO VM.. DSianmtosnod IAnudsotnraelsiaia C10h aracterHizigahtiolignh otsf Aoifr bPorsnte rPs aornti cSualafetety M atter at Urban and Rural Area in Bandung and Lembang Indonesia using Instrumental Neutron Activation Analysis 1U6-:1140/P–1O7 :30 SESMSI.O PNa l5o:m ba Italy Characterization of a Neutron Collimator for Neutron Fast Flux Research Reactors Radiography Applications U-33/PO I. Ionita Romania Optimizing Conditions Suited for Stress Determinations in Q- Chairperson: M.Y. Khalil, Egypt Space Focusing Configurations Co-Chairperson: J. Guidez, France U-34/PO I. Ionita Romania SANS Facility at the PITESTI 14MW TRIGA Reactor No of Paper Name Designating Member U-19/PO A.V. Bychkov Russian Time Title of Paper IAEA-CN-156- State/OrgFaendiezaratitoionn RIAR Capabilities in Support of the Innovative Nuclear T(mecinh)n ologies U-231/O/PRO JA.. GKuliindoevz RFruasnsciaen Federation S2M0 ReactAonr aAlyftseirs Coof rSeo Mdioudme-rCnoizoalteiodn F ast Reactor Operations World-wide and Consequences for Future Reactor U-22/PO V.A. Tsykanov Russian Federation Set of Investigations of HFR Fuel Rods in Justification of their Design and Operation Serviceability and Safe Operation A. Klinov (presented U-31/OR Sby. )G opala Iyengar India 20 Two Decades of Operating Experience with the Fast Breeder Test Reactor U-12/PO C.S. Lee Korea, Republic of Utilization of Irradiation Holes in HANARO U-5/OR M.Y. Khalil Egypt 20 Budget Uncertainty and Minimum Detectable U-27/PO S.H. Ahn Korea, Republic of Design anCdo Inncsetanltlraattioionn so fU Fsuinegl TReeslta Ltioveo,p A inb sHoAluNteA RanOd K0 – IAEA Standardization for the INAA Laboratory of the ETRR-2 U-42/PO S.I. Wu Korea, Republic of Design Characteristics of Cold Neutron Source in HANARO U-20/OR A.V. Bychkov Russian Federation 20 Usage of the BOR-60 Reactor for Investigation of U-47/PO W. Helal Syrian Arab Republic Pure Commercial Gold Foils as Neutron Monitor: Neutron Self- Advanced Fuel Cycles and Materials Shielding Assessment 1206 2171 WNoE oDf PNaEpeSr D AY, 7 NOVEMBER 200Name De 7s ignating Member IAEA-CN-156- State/Organization Title of Paper 08:30–10:00 SESSION 6: S-49/PO NetwYo. rPkeinregt sfo r ResearchI sRraeealc tor Utilization Developing an Ultrasonic NDE System for a Research Reactor Tank Chairperson: S. Gopala Iyengar, India S-70/PO M. Sepielli Italy Neural Networks Application to CRDM and thermo-hydraulic Co-Chairperson: B.S. Yuldashev, Uzbekistan Data Validation NUo-3 o2f/ POap er T. Hosoya DJaepsaignn ating Member ITnivmees tigation of JRR-3 Control Rod Worth changed with Burn Up IAEA-CN-156- Name State/Organization o(mf Fino)l loweTri tFleu eolf EPlaepmeer nts US--7225//POOR IP.N. C. Ghaokldromva n IKAaEzAa khstan P2r0o ject toD Reevpellaocpein tgh eR Cesoenatrroclh a Rnde aPcrtotre Cctoioanli tSioynsst eamnd a Ct tehnet res WWR-K Roef sEexacreclhle Rnceea ctor P. Adelfang S-67/PO (Zp.r Mesaesnoteod by) Malaysia PUSPATI TRIGA Reactor: 25 Years of Safe Operation and Strategies for Ensuring Safety and Security U-44/OR P. Adelfang IAEA 20 IAEA’s Subprogramme on Research Reactors: S-68/PO J. Abdul Karim Malaysia Core CalcTuelacthionno lofg 1yM aWnd PNUoSn-PPAroTlIi fTeRraItGioAn Reactor (RTP) using Continuous Energy Method of Monte Carlo MVP Code System U-46/OR S. Jovanovi Montenegro 20 Research Reactor Utilization in the Mediterranean S-73 A. Jraut Morocco Follow-upR theeg ioCno:m Tmheis Esixopneinrige nocf eth oef CMEoNntMen TeRgIrGo Aa nMda rk II Reactor oPno Ssasfibeitlyit iLeesv feolr Future Cooperation US-106/POOR TS.TA.. SJhoinkahm a JNaigpearnia O20p erationRaol Elex opfe trhien Ocea raani dB Prarnocghra amsm ae Fsa fcoirli tOy potpimena lf oUrt ilization of the NigUerniaiv eRressiteya Rrcehs eRaerachcteorrs- 1in Utilization of Research Reactors S-32/PO M.O. Ogharandukun Nigeria Regulatory Control of the Nigerian Research Reactor (NIRR-1) S-47/PO S. Margeanu Romania Comparative Dose Calculation for TRIGA HEU and LEU Fuel in 10:00–10:30 Coffee Break Nuclear Accident Situations S-8/PO A. Hanioun Syrian Arab Republic Safety Analysis of MNSR Reactor during Reactivity Insertion 10:30–12:00 SESSION 7(Part I): Accident Using the Validated Code PARET Regulatory Aspects and Experience with S-19/PO CurrCe.n Tt iRpepsaeyarkcuhl ReactoTrh Iasislauneds Including Fuel Management Methodology Upgrade of Thai Research Safety Aspects of Core Conversion Reactor (TRR-1/M1) using SRAC Computer Code Chairperson: G. Torres Oviedo, Chile Co-Chairperson: C.D. Perrin, Argentina No of Paper Name Designating Member Time IAEA-CN-156- State/Organization (min) Title of Paper S-29/OR A. Alwani Canada 20 Canadian Experience in Implementing Modern Regulations of Existing Research Reactors B. Howden (presented by) S-31/OR A. Mikulski Poland 20 The Role of Regulatory Authority in Safe Operation of Research Reactors S-33/OR C.D. Perrin Argentina 20 Causal Factors Guide for the Evaluation of Accidents in Research Reactors U-30/OR J. Couturier France 20 Contribution of Research Reactors to the Programmes for Research and Technological Development on the C. Getrey (presented Safety by) 12:00–13:30 Lunch Break 1224 2153 WLISETD NOEFS PDOASYT, E7R NSO V EMBER 2007 13:30–15:10 SESSION 8: Posters: SpeSciafifce tUy tilization Applications Chairperson: A.V. Bychkov, Russian Federation No of Paper Co-Chairperson: S.L. ChaDpelostig, nInadtiinag Member IAEA-CN-156- Name State/Organization Title of Paper No of Paper Name Designating Member Time ISA-E12A/-PCON -156- H. Mazrou SAtlgaeter/iaO rganization S(mafinet)y CoTreit leP aorfa Pmaepteerr s Prediction in Research Reactors using Artificial Neural Networks: A Comparative Study of various U-2/OR T.V. Delorme Netherlands L2e0a rning AElxgpoerritihenmcues with different methods for on-line and off- line detection of small releases of fission products from S-18/PO S. Saadi Algeria Determinifnuge lD eelegmraednattsio ant othf eS eHnOsRor s used for Fuel Assemblies Cooling Temperature Measurement by the Analysis of Thermal U-7/OR J. Medel Ruggero Chile F2l0u ctuatioNnse uNtrooisneic Analysis for the Fission Mo-99 Product by Irradiation of a LEU Target at RECH-1 Reactor S-43/PO B. Djaroum Algeria Upgrading I&C for the Es Salam Research Reactor U-4/OR S. Syarip Indonesia 20 Root Cause Analysis of Swelling Problem in Kartini U-48/PO R. Kulak Australia Training aRneda Qctuoarlification of Reactor Operating Personnel US--263//POOR A..V M. eAsleqkusiteae v RBruaszsiila n Federation E2x0p erimeTnteacl hHneiqaut eT roaf nTsefesrti nAgn athlyes VisV oEf Rth-e1 0IP00R -HRig1h T BRuIGrnAu p Fuel Reactor Rods in MIR Reactor at the Design Basis RIA A.V. Bychkov Parmeters U-1/PO (Wpr.e Cshenetne d by) China Appraisal for the Operation Safety of SPRR-300 in Recent Years US-1441/POOR AJ.. VR.a Vtainj ogradov RCuzessciha nR eFpeudbelriac tion C20a lculatioRnes aalinzda tMioena osfu trheem IeBnRts-2 a Rt tehsee aTrcahin Rinega Rcteoar ctor VR-1 Modernization Programme S-54/PO L. Sklenka Czech Republic Improvements of the Training Reactor VR-1 – Only Way how to b e Attract ive for Students and Scientists S-44/PO F. Foulon France Study of Temperature Effects on ULYSSE Reactor for Training 15:10–16:10 Poster Session (Utilization) with refreshments and Qualification of Operating Personnel S-17/PO SI.E.L. .S Ctahmapaltoetl atos GInrdeieac e M10o nte CaHrliog hSliimghutlsa toiof nP oosf tGerRsR o-n1 UCtoilirzea atinodn N eutron Irradiation Positions Using MCNP S-28/PO F. Tzika Greece Radiological Characterization of the GRR-1 Pool 16:10–17:30 SESSION 9: DecoI.Em.m Sitsasmioanteilnagto asn d Waste Management (presented by) Chairperson: G. Storr, Australia S-71/PO Co-CAh. aAirspzeórdsio n: S. TozseHr,u Hnguanrgy ary The Next 20 Years Operation of the 36 Years Old Hungarian Training Reactor NS-o1 o5f/ PPOa per NT.aMm. eSembiring DInedsoingensaitain g Member VTaimlidea tionT oitfl eth oef MPaopneter Carlo Method of MVP Code on the First IAEA-CN-156- State/Organization C(mritinic)a lity of Indonesian Multipurpose Reactor DS-E1-63//POOR JS.e Rtioyawnlitnog AInudsotnraelsiaia N30e utronicO Avnearlvyiseiws of RSesGe-aGrAchS RSeilaiccidtoer CDoerceo mwimthi sUsrioaniinugm 3 Density of 4,8 g/cm DE-4/OR P.J.C. Dinner IAEA 15 International Decommissioning Network: A New Vehicle S-48/PO D.H. Nugroho Indonesia Fault Posfitoior nS hEasrtiinmga Dtioenc oUmsimngis sCionloinr gS ePglamnennintagt iaond A Epxpproearicehn ctoe the Thermal Infrared Image of a Cabling Network in the Nuclear WM-2/OR M. Pešic Serbia 20 Carbon Steel Construction Removal from Spent Fuel Reactor Storage Pool S-56/PO G.R. Sunaryo Indonesia Water Chemistry Surveillance for Multi Purpose Reactor 30MW GA Siwabessy, Indonesia U-51/PO L. Pandi Indonesia Assessment of Qualification of RSG-GAS Reactor Operator in Indonesia 1242 2135 TFHRUIDRASYD, A9 YN, O8V NEOMVBEEMRB 2E0R0 72 007 08:30–1009:0405 SESSION 71(3P: art II): RPaengeull aDtoisrcyu Asspioenc tosn a Mnda iEn xIspseuriesn c e with Canudrr Tenret nRdess iena rScahf eRtye aMcatonra Igsesmuesn tI nacnldu d ing SUatifleiztayt iAosnp oefc tRse osfe Carocrhe RCeoancvteorsi on Chaiirrperrson:: O. Harbitz, Norway CJ.o L-Coyh,a Airupsetrrsaolian: H. Abou Yehia, IAEA No of Paper Panellists: Name Designating Member Time IAEA-CN-156- K. Brockman, USA State/Organization (min) Title of Paper O. Harbitz, Norway S-59/OR J. ReJp. Wusasradr d, France Australia 20 Regulatory Review Methods: Review of the ANSTO A. Dela Rosa, Phillipines Application for a Facility Licence to Operate the OPAL J. Rowling, Australia Research Reactor in Australia: Case Study Review of R.N. Saxena, Brazil Operational Readiness S-38/OR J.L. MSn. Selcghrnoevied, eUr SA Germany 20 Research Reactors in Germany: An Overview B.S. Yuldashev, Uzbekistan S-42/OR D. Conte France 20 The French Approach for the Regulation of Research Reactors 09:45-10:30 SESSION 14: S-30/OR G. Krzysztoszek Poland 20 MARIA Research Reactor Conversion to LEU Fuel Conclusions and Recommendations Closing 10:00–10:30 Coffee Break Chairperson: Ph. Jamet, IAEA 10:30–12:00 SESSION 10: Core Safety and Utilization Parameters 10:30-11:00 Coffee Break Chairperson: N. Arkhangelsky, Russian Federation Co-Chairperson: J.L. Snelgrove, USA 11:00 Depart for Technical Tour No of Paper Designating Member Time IAEA-CN-156- Name State/Organization (min) Title of Paper approx.18:00 Return to Sydney S-36/OR J.L. Snelgrove USA 30 Status Report on Preparation of IAEA Guidelines for Qualification of Research Reactor Fuels S-13/OR C. Park Korea, Republic of 20 Simulation of flow behavior in the HANARO reactor pool by using the MARS code S-27/OR B. Sevdik Turkey 20 Experimental Measurements for Plate Temperatures of MTR Fuel Elements at Sudden Loss-of-Flow Accident and Comparison with Computed Results S-60/OR D.F. Hergenreder Argentina 20 Contract Performance Demonstration Test in the OPAL 12:00–13:20 Lunch Break 1260 2117 THURSDAY, 8 NOVEMBER 2007 13:20–15:20 SESSION 11: Programmes for the Minimization of the Use of HEU Chairperson: P. Lemoine, France (P) Co-Chairperson: P. Adelfang, IAEA No of Paper Designating Member Time IAEA-CN-156- Name State/Organization (min) Title of Paper F-8/OR S.L. Dickerson USA 30 Status of the United States Department of Energy's Nuclear Fuel Return Programmes F-11/OR J. Roglans-Ribas USA 30 Conversion of Research and Test Reactors to Low Enriched Uranium Fuel: Technical Overview and Programme Status F-12/OR P. Lemoine France 30 High Density Fuel Development for Research Reactors D. Wachs USA S-35/OR O.C. Reistad Norway 20 Measuring Progress in Reactor Conversion and HEU Minimization Towards 2020 - The Case of HEU-fuelled Research Facilities 15:20–16:20 Poster Session (Fuel) with refreshments J.L. Snelgrove USA 10 Highlights of Posters on Fuel 16:20–17:40 SESSION 12: New Research Reactor Projects Chairperson: A. Dela Rosa, Philippines Co-Chairperson J. Roglans-Ribas, USA No of Paper Designating Member Time IAEA-CN-156- Name State/Organization (min) Title of Paper S-21/OR A. Irwin Australia 20 OPAL: Commissioning a New Research Reactor S-23/OR K.A. Konoplev Russian Federation 20 Reactor PIK Status of Construction S-37/OR M. Summerfield Australia 20 Licensing of the OPAL Reactor during Construction and Commissioning S-24/PO Y. Lobach Ukraine 20 Concept for a New Research Reactor in Ukraine 18 19 FTRHIUDRASYD, A9 YN,O 8V NEOMVBEEMRB 2E0R0 72 007 08:30–0190:4050 SESSION 173(P: art II): PRaengeull aDtiosrcyu Assipoenc tosn a Mndai nE xIspseuriesn c e with aCnudrr Ternetn Rdess iena Srcahfe Rtye aMcatonra gIsesmuesn tI nacnldu d ing USatifleiztayt iAosnp oefc Rtse osfe aCrocrhe RCeoancvteorsi on Chaiirrperrson:: O. Harbitz, Norway JC.o L-Coyh,a Airupsetrrasloian: H. Abou Yehia, IAEA No of Paper Panellists: Designating Member Time IAEA-CN-156- K. BNroacmkeman, USA State/Organization (min) Title of Paper O. Harbitz, Norway S-59/OR J. ReJp. Wusasradr d, France Australia 20 Regulatory Review Methods: Review of the ANSTO A. Dela Rosa, Phillipines Application for a Facility Licence to Operate the OPAL J. Rowling, Australia Research Reactor in Australia: Case Study Review of R.N. Saxena, Brazil Operational Readiness S-38/OR J.L. MSn. Selcghrnoevied, eUr SA Germany 20 Research Reactors in Germany: An Overview B.S. Yuldashev, Uzbekistan S-42/OR D. Conte France 20 The French Approach for the Regulation of Research Reactors 09:45-10:30 SESSION 14: S-30/OR G. Krzysztoszek Poland 20 MARIA Research Reactor Conversion to LEU Fuel Conclusions and Recommendations Closing 10:00–10:30 Coffee Break Chairperson: Ph. Jamet, IAEA 10:30–12:00 SESSION 10: Core Safety and Utilization Parameters 10:30-11:00 Coffee Break Chairperson: N. Arkhangelsky, Russian Federation Co-Chairperson: J.L. Snelgrove, USA 11:00 Depart for Technical Tour No of Paper Designating Member Time IAEA-CN-156- Name State/Organization (min) Title of Paper approx.18:00 Return to Sydney S-36/OR J.L. Snelgrove USA 30 Status Report on Preparation of IAEA Guidelines for Qualification of Research Reactor Fuels S-13/OR C. Park Korea, Republic of 20 Simulation of flow behavior in the HANARO reactor pool by using the MARS code S-27/OR B. Sevdik Turkey 20 Experimental Measurements for Plate Temperatures of MTR Fuel Elements at Sudden Loss-of-Flow Accident and Comparison with Computed Results S-60/OR D.F. Hergenreder Argentina 20 Contract Performance Demonstration Test in the OPAL 12:00–13:20 Lunch Break 2106 1271 LWISETD NOEFS PDOASYT, E7R NSO VEMBER 2007 13:30–15:10 SESSION 8: Posters: SpeSciaffice tUy tilization Applications Chairperson: A.V. Bychkov, Russian Federation No of Paper Co-Chairperson: S.L. Chaplot, India IAEA-CN-156- Name Designating Member State/Organization Title of Paper No of Paper Designating Member Time SIA-E12A/-PCON -156- HN.a Mmaezrou ASltgaeteri/aO rganization S(mafine)ty CoTreitl eP aorfa Pmaepteerr s Prediction in Research Reactors using Artificial Neural Networks: A Comparative Study of various U-2/OR T.V. Delorme Netherlands L2e0a rning EAxlgpoerritiehnmcues w ith different methods for on-line and off- line detection of small releases of fission products from S-18/PO S. Saadi Algeria Determinifnuge lD eelegmraednattsio ant othf eS HenOsRor s used for Fuel Assemblies Cooling Temperature Measurement by the Analysis of Thermal U-7/OR J. Medel Ruggero Chile F2l0u ctuatioNnes uNtrooinseic Analysis for the Fission Mo-99 Product by Irradiation of a LEU Target at RECH-1 Reactor S-43/PO B. Djaroum Algeria Upgrading I&C for the Es Salam Research Reactor U-4/OR S. Syarip Indonesia 20 Root Cause Analysis of Swelling Problem in Kartini U-48/PO R. Kulak Australia Training aRneda Qctuoar lification of Reactor Operating Personnel SU--263//POOR A.. VM. eAslqekusiteae v BRruaszsili an Federation E20xp erimeTnetaclh Hneiqaut eT oraf nTsefestri nAgn athlyes VisV oEf Rth-e1 0IP00R -HRig1h T BRuIGrnAu p Fuel Reactor Rods in MIR Reactor at the Design Basis RIA A.V. Bychkov Parmeters U-1/PO W(pr. eCsheennte d by) China Appraisal for the Operation Safety of SPRR-300 in Recent Years SU-1441/POOR JA.. VR.a Vtainj ogradov CRzuescshia nR eFpeudbelrica tion C20a lculatioRnesa alinzda tMioena osfu trheem IeBnRts-2 a Rt tehsee aTrcahin Rinega Rcteoar ctor VR-1 Modernization Programme S-54/PO L. Sklenka Czech Republic Improvements of the Training Reactor VR-1 – Only Way how to b e Attract ive for Students and Scientists S-44/PO F. Foulon France Study of Temperature Effects on ULYSSE Reactor for Training 15:10–16:10 Poster Session (Utilization) with refreshments and Qualification of Operating Personnel S-17/PO IS.E.L. .S Ctahmapaltoetl atos GInrdeieac e M10o nte CaHrliog hSliimghutlsa toiof nP oosf tGerRsR o-n1 UCtoilirzea atinodn N eutron Irradiation Positions Using MCNP S-28/PO F. Tzika Greece Radiological Characterization of the GRR-1 Pool 16:10–17:30 SESSION 9: DecoI.Em.m Sitsasmioanteilnagto asn d Waste Management (presented by) Chairperson: G. Storr, Australia S-71/PO Co-CAh. aAirspzeórdsio n: S. TozseHru, nHguanrgy ary The Next 20 Years Operation of the 36 Years Old Hungarian Training Reactor SN-o1 5o/fP POa per TN.aMm. eSembiring IDnedsoingensaitain g Member VTaimlidea tion of the Monte Carlo Method of MVP Code on the First IAEA-CN-156- State/Organization (m Title of Paper Criitnic)a lity of Indonesian Multipurpose Reactor SD-E1-63//POOR SJ.e Rtioyawnlitnog IAnudsotnraelsiaia N30e utronicO Avnearvlyiesiws of RSesGe-aGrcAhS R Seilaiccitdoer CDoerceo mwimthi sUsrioaniinugm 3 Density of 4,8 g/cm DE-4/OR P.J.C. Dinner IAEA 15 International Decommissioning Network: A New Vehicle S-48/PO D.H. Nugroho Indonesia Fault Posfiotior nS hEasrtiinmga Dtioenc oUmsmingis sCionloinr gS ePglamnennintagt iaonnd A Epxppreoraiechn cteo the Thermal Infrared Image of a Cabling Network in the Nuclear WM-2/OR M. Pešic Serbia 20 Carbon Steel Construction Removal from Spent Fuel Reactor Storage Pool S-56/PO G.R. Sunaryo Indonesia Water Chemistry Surveillance for Multi Purpose Reactor 30MW GA Siwabessy, Indonesia U-51/PO L. Pandi Indonesia Assessment of Qualification of RSG-GAS Reactor Operator in Indonesia 2124 1253 WNoE oDf PNaEpeSr D AY, 7 NOVEMBER 2007 Name Designating Member IAEA-CN-156- State/Organization Title of Paper 08:30–10:00 SESSION 6: S-49/PO NetwYo. rPkeinregt sfo r ResearchI sRraeealc tor Utilization Developing an Ultrasonic NDE System for a Research Reactor Tank Chairperson: S. Gopala Iyengar, India S-70/PO M. Sepielli Italy Neural Networks Application to CRDM and thermo-hydraulic Co-Chairperson: B.S. Yuldashev, Uzbekistan Data Validation UN-o3 o2f/ PPOa per T. Hosoya JDaepsaignn ating Member ITnivmees tigation of JRR-3 Control Rod Worth changed with Burn Up IAEA-CN-156- Name State/Organization o(mf Fino)l loweTri tFleu oefl EPlaepmeer nts SU--7225//POOR PI.N. C. Ghaokldromva n KIAaEzAak hstan P20ro ject toD Reevpellaocpein tgh eR Cesoenatrroclh a Rneda Pcrtotre Cctoioanlit iSoynst eamnd a Ct tehnet res WWR-K Roef sEexacreclhle Rnceea ctor P. Adelfang S-67/PO Z(p. rMesaesnoteod by) Malaysia PUSPATI TRIGA Reactor: 25 Years of Safe Operation and Strategies for Ensuring Safety and Security U-44/OR P. Adelfang IAEA 20 IAEA’s Subprogramme on Research Reactors: S-68/PO J. Abdul Karim Malaysia Core CalcTuelacthionno lofg 1y ManWd PNUoSn-PPAroTlIi fTerRaItGioAn Reactor (RTP) using Continuous Energy Method of Monte Carlo MVP Code System U-46/OR S. Jovanovi Montenegro 20 Research Reactor Utilization in the Mediterranean S-73 A. Jraut Morocco Follow-upR tehgei oCno:m Tmheis Esixopneinrige nocf eth oef CMEoNntMen TeRgrIGo Aan Md ark II Reactor oPno Ssasifbeitlyit iLees vfeolr Future Cooperation SU-106/POOR ST.TA.. SJhoinkaahm a NJaigpearnia O20p erationRaol lEex opfe trhien Ocea raani dB rParnocghra ams ma eFsa fcoilri tOy potpimena lf oUrt ilization of the NigUerniaiv eRressitey aRrcehs eRaercahcetorrs- 1in Utilization of Research Reactors S-32/PO M.O. Ogharandukun Nigeria Regulatory Control of the Nigerian Research Reactor (NIRR-1) S-47/PO S. Margeanu Romania Comparative Dose Calculation for TRIGA HEU and LEU Fuel in 10:00–10:30 Coffee Break Nuclear Accident Situations S-8/PO A. Hanioun Syrian Arab Republic Safety Analysis of MNSR Reactor during Reactivity Insertion 10:30–12:00 SESSION 7(Part I): Accident Using the Validated Code PARET Regulatory Aspects and Experience with S-19/PO CurrCe.n Tt iRpepsaeyarkcuhl ReactoTrh Iasislauneds Including Fuel Management Methodology Upgrade of Thai Research Safety Aspects of Core Conversion Reactor (TRR-1/M1) using SRAC Computer Code Chairperson: G. Torres Oviedo, Chile Co-Chairperson: C.D. Perrin, Argentina No of Paper Designating Member Time IAEA-CN-156- Name State/Organization (min) Title of Paper S-29/OR A. Alwani Canada 20 Canadian Experience in Implementing Modern Regulations of Existing Research Reactors B. Howden (presented by) S-31/OR A. Mikulski Poland 20 The Role of Regulatory Authority in Safe Operation of Research Reactors S-33/OR C.D. Perrin Argentina 20 Causal Factors Guide for the Evaluation of Accidents in Research Reactors U-30/OR J. Couturier France 20 Contribution of Research Reactors to the Programmes for Research and Technological Development on the C. Getrey (presented Safety by) 12:00–13:30 Lunch Break 2142 1235 PToUsEteSrsD: AY, 6 NOUtVilEizaMtiBonE R 2007 13:30–15:10 SESSION 4 (Part II): No of Paper Safety Management and DOpeName esi rgantaiotinga lM Seamfebtey r IAEA-CN-156- State/Organization Title of Paper Chairperson: J. Boogaard, Netherlands U-54/PO Co-CMh. aHirapqeures on: A. SapoBzhannigklaodve, sRhu ssian Operating Experience Utilization Programmes of the BAEC 3 MW Federation TRIGA Mark-II Research Reactor in Bangladesh U-55/PO S. Abdul Latif Bangladesh Studies on Environmental Pollution in Bangladesh Using Reactor No of Paper Name Designating Member BTiamse d NeutIAEA-CN-156- State/Organization (min) Tit rleo no fA Pcatipvaetri on Analysis Technique U-8/PO R. Pugliesi Brazil Improvement on Sensitivity for the Track - Etch Neutron S-51/OR J. Couturier France R20a diograpPheyr iodic Safety Review Management for French D Rive (presented Research Reactors - Technical Support Organization U-10/PO A. Soares Leal Brazil New Perspectives for the TRIGA IPR-R1 Research Reactor by) Approach U-15/PO C.B.R. Parente Brazil First Experiments in the IPEN-CNEN/SP PSD Neutron Powder S-57/OR A.S. Vieira Neto Brazil D20if fractomEextpeer rience of IPEN-CNEN/SP in the Execution of the First Phase of the Safety Culture Enhancement U-45/PO K. Ilieva Bulgaria Future UtPilirzoagtiroanm omf eth aet RIEeAse-Ra1rc Bh rRazeialicatno rR IeRsTe ainr cSho Rfiae aacftteorr its Reconstruction S-58/OR J.-S. Wu Korea, Rep. of 20 Development of Safety Performance Indicators for U-38/PO M. Marek Czech Republic UtilizationH oAf NthAeR LOVR-15 Research Reactor at Rež US--4496//POOR SK.. MMaartgejekaan u CRzoemcahn Riae public U20ti lizationE omf ethrgee VnRcy-1 I nTtrearivneinngti oRne Palcatno rf o r 14 MW TRIGA - Pitesti U-28/PO I.H. Auterinen Finland The 250 kRWe sFeiaRr c1h T RReIaGcAto Rr esearch Reactor - International Role i n Boron N eutron Capture Therapy (BNCT) and Regional Role in Isotope Production, Education and Training 1U5-:5160/P–1O6:10 Poster Session ( 125 T.M. SoentonSoa fety) wInitdho nreefsrieas hments Feasibility Study of I Brachytherapy in Indonesia U-17/PO VM.. DSianmtosnod IAnudsotnraelsiaia C10h aracterHizigahtiolignh otsf Aoifr bPorsnte rPs aornti cSualafetety M atter at Urban and Rural Area in Bandung and Lembang Indonesia using Instrumental Neutron Activation Analysis 1U6-:1140/P–1O7 :30 SESMSI.O PNa l5o:m ba Italy Characterization of a Neutron Collimator for Neutron Fast Flux Research Reactors Radiography Applications U-33/PO I. Ionita Romania Optimizing Conditions Suited for Stress Determinations in Q- Chairperson: M.Y. Khalil, Egypt Space Focusing Configurations Co-Chairperson: J. Guidez, France U-34/PO I. Ionita Romania SANS Facility at the PITESTI 14MW TRIGA Reactor No of Paper Name Designating Member UIA-E19A/-PCON -156- A.V. Bychkov RStussian Federation Time Title of ate/Organization RIAR Capabilities P ainp Seru pport of the Innovative Nuclear T(mecinh)n ologies U-231/O/PRO AJ.. GKuliindoevz RFruasnsciaen Federation S2M0 ReactAonr aAlyftseirs Coof rSeo Mdioudme-rCnoizoaletiodn F ast Reactor Operations World-wide and Consequences for Future Reactor U-22/PO V.A. Tsykanov Russian Federation Set of Investigations of HFR Fuel Rods in Justification of their Design and Operation Serviceability and Safe Operation A. Klinov (presented U-31/OR bSy. )G opala Iyengar India 20 Two Decades of Operating Experience with the Fast Breeder Test Reactor U-12/PO C.S. Lee Korea, Republic of Utilization of Irradiation Holes in HANARO U-5/OR M.Y. Khalil Egypt 20 Budget Uncertainty and Minimum Detectable U-27/PO S.H. Ahn Korea, Republic of Design anCdo Inncsetanltlraattioionn so fU Fsuinegl TReeslta Ltioveo,p A inb sHoAluNteA RanOd K0 – IAEA Standardization for the INAA Laboratory of the ETRR-2 U-42/PO S.I. Wu Korea, Republic of Design Characteristics of Cold Neutron Source in HANARO U-20/OR A.V. Bychkov Russian Federation 20 Usage of the BOR-60 Reactor for Investigation of U-47/PO W. Helal Syrian Arab Republic Pure Commercial Gold Foils as Neutron Monitor: Neutron Self- Advanced Fuel Cycles and Materials Shielding Assessment 2160 1217 TNUo oEf SPDapAerY , 6 NOVEMBER 2007 Designating Member IAEA-CN-156- Name State/Organization Title of Paper 08:30–12:00 SESSION 4(Part I): U-50/PO SafeSty. NMilasnuawgaenmkeonsti ta nd TOhpaeilraantido nal Safety Implementation of TRR-1/M1 for Thailand’s Nuclear Engineering Programme Chairperson: J. Repussard, France Co-Chairperson: C. Maloney, Australia PNos otef rPsa: per Fuel Designating Member Time IAEA-CN-156- Name State/Organization (min) Title of Paper S-5/OR M.H. Voth USA 20 Improvements in the Management of Safety in No of Paper Name Designating Member Title of PaRpesre arch Reactor Operation through Appropriate IAEA-CN-156- State/Organization Application of Selected Power Reactor Good Practices FS--44/1P/OOR GJ.. JB.o Sotgoarra rd ANuesthtrearlliaan ds C20o nvertinSga HfeIFtyA MRa tnoa Lgoewm Eenntr iacht eNdR UGr-aPneiuttmen F uel FS--65/2P/OOR SD.. KS.a Srkhaurk la AInudsiatr alia T2h0e ReguSlaatfoertyy RMoalen aogf ethmee Antu asntrda lEiafnfe Rctaivdeia Utiotinliz Partiootne cotfio Inn daiannd Nuclear SRaefesteya Arcghe nRcayc itno rrse lAaPtioSnA tRoA S, pCeInRtU FSu ealn adr iDsiHngR fUroVmA Research Reactors in Australia S-45/OR M. Latif Pakistan 20 Ageing Management of Pakistan Research Reactor-1 F-7/PO J.A. Sarta Fuentes Colombia Design an(Pd AcRonRs-t1ru) ction of a Decay Pool at IAN-R1 Research Reactor S-40/OR G. Bignan France 20 The Safety Reassessment of Research Reactors in DE-1/PO J. Kaulard Germany Safety AsFsreasnscmeent for Decommissioning of Research Reactors – International Project on Evaluation and Demonstration of Safety S. Thierfeldt during Decommissioning of Nuclear Facilities (DeSa) 10:10–10:30 Coff(epere Bsreenatekd by) WM-4/PO A. Savidou Greece Further Development in Characterization of Radioactive Waste S-50/OR J. Repussard France D30ru ms byC Noomnp Dateibsitlriutyc toivf eS aGfaemty manad S Specutrroitmy etry at GRR-1 FS--12/5P/O R AM..C C. iDorcaagnoelsiciu Romaniia A2l0-C lad SOpepnetr aNtuiocnleaal rS Faufeetly C Eoxrproesrieonc Set uadt i1e4s MatW M aTgRuIGreAle Site, Romania Research Reactor from INR Pitesti, Romania FS--23/4P/O R MA.. Persšici Selorvbeian ia V2I0N CA SiLteju Pbrljeapnaar aTtRioInG fAo rM SApRenKt IFI:u 4e0l SYheiaprms eonf tS uccessful Operation WM-5/PO Dung Tran Vietnam Experimental Study of Systematic Errors of Gamma for Assay of S-39/OR S. Nitiswati Indonesia R20a dioactivAeg eWinags tMe aDnraugmesm ent Programme of Kartini Reactor for Safe Operation 12:00–13:30 Lunch Break 288 29 PARTICIPATION IN IAEA SCIENTIFIC MEETINGS MONDAY, 5 NOVEMBER 2007 DOCUMENT Governments of Member States and those organizations whose NUMBER TITLE YEAR a1c3t:i3v0iti–e1s7 a:0re0 releSvEaSnSt ItOo Nth e3 :m eeting subject matter are invited to d esignate partiSciupsatnatisn abinl e UIAtEiliAz atsiocnie natnifdic Stcraotnefegriensc es and No. SF-1 EUROPEAN ATOMIC ENERGY 2006 symposia. In addition, the IAEA itself may invite a limited number COMMUNITY, FOOD AND o f scientists as iCnhviateirdp esrpseoank:e rs. OR.nNly. Spaarxteicnipaa, nBtsra dzeils ignated or AGRICULTURE ORGANIZATION OF i nvited in this waCyo a-Creh aeinrtpitelerds oton :p Sr.eKs.e Pnta rpaanpjepres, aIAnEd Ata ke part in THE UNITED NATIONS, the discussions. INTERNATIONAL ATOMIC ENERGY No of Paper Name Designating Member Time Title of PAapGeEr NCY, INTERNATIONAL LABOUR RIAeEpAre-CseNn-t1a5ti6v-e s of the press, radio, Sttaetlee/vOisrigoann izoart iono ther (min) ORGANIZATION, INTERNATIONAL iUnf-o1r1m/OatRio n media aSn.Ld. Cmheampbloetr s of the Inpduiab lic, the latter as 30 UtilizationM PArRoIgTrIaMmEm OesR GFoArN LIoZwA TAInOdN M, OedEiCumD Flux “observers”, may also be authorized to attend, but without the ResearchN RUeCaLcEtoArRs ENERGY AGENCY, PAN right to take part in the proceedings. AMERICAN HEALTH ORGANIZATION, F-3/OR L. Ramanathan Brazil 20 A CorrosUioNn IMTEoDni tNorAinTgIO PNroSg rEaNmVmIReO foNr MREeNseTa rch Scientists interested in participating in any of the IAEA meetings Reactor Spent Fuel Basins PROGRAMME, WORLD HEALTH lUis-te4d0 /OinR this prograRm.Nm.e S asxheonuald requestB irnafzoirl mation from the 20 The IEA-OR1R GRAesNeIaZrAcThI OReNa, cFtourn:d 5a0m YeEnAtaRl Sa ofef tOy perating governmental authorities of their own countries, in most cases ExperienPceri nacnidp leUsti:l iSzatfieotny fFour nRdeasmeeanrctahl,s T eaching and the Ministry of Foreign Affairs or national atomic energy authority. Radioisotopes Production U-43/OR B.S. Yuldashev Uzbekistan I2A0E A-TECTDheO CUstilization of 10 MW Research Reactor in Tashkent PUBLICATIONS P15ro:1c0e–e1d5in:4g0s Coffee Break 792 INTERNATIONAL ATOMIC ENERGY 1995 AGENCY, Management of Research TUh-e1 3p/rOoRce edings of Bth.eJ .cBo.n Nfeyraernkcoe will be Gphuabnlisah ed by the IAEA 20 The 30 kWRe Racetsoer aArcghe iRnge actor Facility in Ghana: Past, in unedited form as a CD-Rom and will be sent to all participants Present and Future Programmes 1212 Strategic Planning for Research 2001 aUft-e1r8 t/hOeR m eeting. W.H.A. Beere Norway 20 The HaldRene aRcetoarcstor Project: Experience gained in International Research Orders U-35/OR M.I. Itoh Japan 12207 3 The UtilizDaetioconm omf Risessioenairncgh TReecahcntoiqruse asn fdo rr elated 2002 IAEA publications may be ordered at the Conference Desk or Facilities Rfoers tehaer cShu pRpeoarctitnogrs o f Innovative Power directly from the Sales and Promotion Unit Reactor and Related Fuel Cycle International Atomic Energy Agency, P.O. Box 100 1374 Development Status of Metallic, 2003 1U4-090/O VRie nna, AustriaR . Rosa Italy 20 RACE-T DEixsppeerrismioenn taanl dA cNtiovnit-ieosx id- eA nA dOvvaenrcveiedw of the Fax: (+43 1) 2600-29302 Subcritical Measurements Preliminary to the and Alternative Fuels for Power and Email: sales.publications@iaea.org Accelerator Coupling Experiment Research Reactors Internet: http://www.iaea.org/books 19:00 Conference Dinner 1387 INTERNATIONAL ATOMIC ENERGY 2004 AGENCY, Safety Considerations for Research Reactors in Extended Shutdown 1508 Spent Fuel Management Options for 2006 Research Reactors in Latin America Technical Report Series TRS 418 Corrosion of Research Reactor 2003 Aluminium Clad spent Fuel in Water TRS 443 Understanding and Managing Ageing of 2006 Material in Spent Fuel Storage Facilities 360 371 DSOUCNUDMAENYT, 4 NOVEMBER 2007 TITLE YEAR DOCUMENT NUMBER NUMBER TITLE YEAR 16:00–19:00 Registration No. SF-1 EUROPEAN ATOMIC ENERGY 2006 TRS 446 Decommissioning of Research 2006 WeClcOoMmMeU RNeIcTeYp, tFioOnO D AND Reactors: Evolution, State of the Art, AGRICULTURE ORGANIZATION OF Open Issues THE UNITED NATIONS, INTERNATIONAL ATOMIC ENERGY TRS 455 Utilization Related Design Features of 2007 AGENCY, INTERNATIONAL LABOUR Research Reactors: A Compendium ORGANIZATION, INTERNATIONAL MONDAY, 5 NMOAVREITMIMBEE ORR G20A0N7IZ ATION, OECD Proceedings Research Reactor Utilization, Safety 2005 NUCLEAR ENERGY AGENCY, PAN Series Decommissioning, Fuel and Waste 08:30 ReAgMisEtrRaItCioAnN HEALTH ORGANIZATION, Management, Proceedings of an UNITED NATIONS ENVIRONMENT International Conference held in PROGRAMME, WORLD HEALTH Santiago, Chile, 10-14 November 2003 09:30–10:30 SESSION 1: WeOlcRoGmAeN &IZ AOTpIeOnNin, gF uAndddarmesesnetasl :S afety Miscellaneous INTERNATIONAL ATOMIC ENERGY 2004 Principles: Safety Fundamentals AGENCY, The Code of Conduct on the Representative of Australia Safety of Research Reactors Representative of the IAEA IAEA-TECDOCs 10:30–10:45 Coffee Break 792 INTERNATIONAL ATOMIC ENERGY 1995 10:45–12:15 SEASGSEIONNC Y2:, Management of Research ExRpearicetnocr eA gweiitnhg t he Code of Conduct on the Safety of Research Reactors 1212 Strategic Planning for Research 2001 ChRaeirapcetorsrson: L. Keen, Canada Co-Chairperson: J. Loy, Australia 1273 Decommissioning Techniques for 2002 No of Paper Research Reactors Name Designating Member Time IAEA-CN-156- State/Organization (min) Title of Paper 1374 Development Status of Metallic, 2003 S-1/OR J. Loy Australia 30 Where to with the Code of Conduct on the Safety of Dispersion and Non-oxide Advanced Research Reactors (Invited) and Alternative Fuels for Power and S-69/OR ReHs.e Aabrcohu R Yeeahcitao rs IAEA 20 Feedback from the Regional Meetings on the Application of the Code of Conduct and Updating of the 1387 INTERNATIONAL ATOMIC ENERGY 2004 IAEA Programme on Research Reactors Safety AGENCY, Safety Considerations for S-3/OR ReAs.e Saarcpho zRhenaicktoovrs in ExRteunssdieadn Federation 20 Effectiveness of Safety Regulation at Russian Research Reactors in Compliance with International Practice Shutdown S-4/OR S. Tozser Hungary 20 Some Operational Aspects of BRR's Management 1508 Spent Fuel Management Options for 2006 System with Respect to the Code of Conduct Research Reactors in Latin America 12:15–13:30 Lunch Break Technical Report Series TRS 418 Corrosion of Research Reactor 2003 Aluminium Clad spent Fuel in Water TRS 443 Understanding and Managing Ageing of 2006 Material in Spent Fuel Storage Facilities 342 353 FTOIMRTEHTCAOBMLINEG SCIENTIFIC MEETINGS SCHEDULED BY 13:30-15:10 Session 8 NOTES THE IAEA Specific Utilization Applications Monday, 5 November 2007 15:10-16:10 Poster Session with refreshments 2007 08:30 Registration 16:10-17:30 Session 9 International Symposium on Clinical PET and Molecular Medicine Decommissioning and Waste Management 10-14 November, Bangkok, Thailand 09:30-10:30 Session 1 International ConfeWreenlccoem oen &Ill iOcipt eNnuinclge aArd Tdrraefsfisceksin g: Thursday, 8 November 2007 C10o:l3le0c-t1iv0e:4 E5x pe rienCcoeff eaen dB trheea kW ay Forward 19-22 November, Edinburgh, UK 08:30-10:00 Session 7(Part II) 10:45-12:15 Session 2 10:00-10:30 Coffee Break Experience with the Code of Conduct on the 2008 Safety of Research Reactors 10:30-12:00 Session 10 12:15-13:30 Lunch Break International Conference on Topical Issues in Nuclear Installation Core Safety and Utilization Parameters Safety, 12:00-13:20 Lunch Break 13:30-15:10 Session 3 Ensuring Safety for Sustainable Nuclear Development Sustainable Utilization and Strategies Mumbai, India 13:20-15:20 Session 11 15:10-15:40 Coffee Break Programmes for the Minimization of the Use of International Symposium on Induced Mutations in Plants HEU 1125-:1450 -A17u:g0u0s t, V ienSneas,s Aiouns 3tr icao n’t 15:20-16:20 Poster Session with refreshments 19:00 Conference Dinner nd 22 IAEA Fusion Energy Conference 16:20-17:40 Session 12 13-18 October, Geneva, Switzerland New Research Reactor Projects Tuesday, 6 November 2007 International Conference on Nuclear Security: Global Directions f0o8r :t3h0e- 1F0u:t1u0r e Session 4(Part I) Friday, 9 November 2007 December, ViennaS, aAfuestytr Mia anagement and Operational Safety 10:10-10:30 Coffee Break 08:30-09:45 Session 13 For information on forthcoming scientific meetings, Panel Discussion p1l0e:a3s0e-1 c2o:n0s0u lt t he SIAesEsAio wne 4b( Psaitert: Ih) tctpo:n//’tw ww.iaea.org/ 09:45-10:30 Coffee Break 12:00-13:30 Lunch Break 10:30-11:00 Session 14 13:30-15:10 Session 4(Part II) Concluding Remarks and Closing 15:10-16:10 Poster Session with refreshments 11:00 Depart for Technical Tour Return to Sydney 16:10-17:30 Session 5 approx. 18:00 Fast Flux Research Reactors Wednesday, 7 November 2007 08:30-10:00 Session 6 Networking for Research Reactor Utilization 10:00-10:30 Coffee Break 10:30-12:00 Session 7(Part I) Regulatory Aspects and Experience with Current Research Reactor Issues Including Safety Aspects of Core Conversion 12:00-13:30 Lunch Break 324 335 ference onon Re C se International Atomic Energy Agency IAEA-CN-156 P.O. Box 100 Wagramer Strasse 5 Sydney A–1400 Vienna, Austria Ma 5–9 November 2007n tili Tel: +43 1 2600 0 agem tive U Fax: +43 1 2600 7 ent and Effec offi cial.mail@iaea.org PROGRAMME Organized by the International Atomic Energy Agency (IAEA) Hosted by the Government of Australia through the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) 07-30891-CN156-Sydney-prog1.indd 1 2007-09-06 14:55:02 International zation h Reactorsc ar e Saf