ANSTO :: Browsing by Author "Reinhard, MI"

Browsing by Author "Reinhard, MI"

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2nd generation microdosimeter with guard ring: an IBC study
(Australian Institute of Nuclear Science and Engineering (AINSE), 2009-11-25) Ziebell, AL; Hu, N; Lai, NS; Lim, WH; Reinhard, MI; Prokopovich, DA; Siegele, R; Dzurak, AS; Rosenfeld, AB
Silicon-on-insulator (SOI) micro dosimeters have recently been used to successfully measure the radiobiological properties of mixed radiation fields typical of medical, space and radiation protection environments. These SOI devices consist of a 2D array of elongated parallelepiped diode structures. Charge collection studies have revealed that due to the electric field distribution within the planar SV, there are significant lateral charge diffusion effects which complicate charge collection and give rise to a less than ideal chord length variance. © 2009 AINSE
3D sensitive volume microdosimeter with improved tissue equivalency: charge collection study and its application in 12C ion therapy
(IOP Publishing, 2018-02-06) James, B; Tran, LT; Bolst, D; Prokopovich, DA; Reinhard, MI; Lerch, MLF; Petasecca, M; Guatelli, S; Povoli, M; Kok, A; Matsufuji, N; Jackson, M; Rosenfeld, AB
This research focuses on the characterisation of a new 3D sensitive volume (SV) microdosimeter covered with polyimide – a material which closely mimics human tissue. The electrical and charge collection properties of the device were investigated and its application in 12C ion therapy were studied. Charge collection studies revealed uniform charge collection and no cross talk between adjacent SVs. To study the microdosimetric response in 12C ion therapy, the new polyimide mushroom microdosimeter were placed at various positions along the central axis of a 290 MeV/u 12C ion spread out Bragg peak (SOBP) at the Heavy Ion Medical Accelerator in Chiba (HIMAC), Japan. From these microdosimetric spectra, dose mean lineal energy $(\overline{{y}_{D})}$ and RBE10 results were obtained, with RBE10 increasing from 1.3 at the entrance to 2.7 at the end of the SOBP. The results obtained in this work show that the new generation of mushroom microdosimeters, covered with tissue equivalent polyimide material, are a useful tool for quality assurance in heavy ion therapy applications. © Open Access - CC BY - IOP Publishing Ltd.
Activity measurements of the radionuclide 153Sm for the ANSTO, Australia in the ongoing comparison BIPM.RI(II)-K1.Sm-153
(Institute of Physics, 2005-01-01) Ratel, G; Michotte, C; Reinhard, MI; Alexiev, D; Mo, L
In 2004, the Australian Nuclear Science and Technology Organisation (ANSTO) submitted two samples of known activity of 153Sm to the International Reference System (SIR). The value of the activity submitted was about 920 MBq. This key comparison result has been added to the matrix of degrees of equivalence in the key comparison database that now contains five results, identifier BIPM.RI(II)-K1.Sm-153. © 2005, Institute of Physics
ANSTO Nuclear Foresnics Research Facility: method development and applications
(Australian Nuclear Science and Technology Organisation, 2012-10-16) Wotherspoon, ATL; Hill, DM; Keegan, EA; Evans, T; Blagojevic, N; Loi, E; Toole, K; Griffiths, GJ; Smith, KL; Reinhard, MI
The IAEA defines nuclear forensic science, commonly shortened to “nuclear forensics” as ‘the scientific analysis of nuclear or other radioactive material, or of other evidence that is contaminated with radioactive material, in the context of legal proceedings, including administrative, civil, criminal or international law’1. In broad terms, the job of the nuclear forensic scientist is to support investigations that involve a nuclear security event. Nuclear forensic examinations will provide information to key questions posed by the investigative authority: What is it? How much is there? Is there any more out there? Is it ours? As an investigation proceeds other questions that may arise are; How old is it? What contaminants are present? Does it pose a threat? Who is responsible for the loss? Where did the material come from? Many of the techniques required to answer these questions are based on environmental radiochemistry. The Nuclear Forensic Research Facility (NFRF) at ANSTO is developing expertise in analysing nuclear and other radioactive material material based upon the precepts of the ‘model action plan’ of the International Technical Working Group for Nuclear Forensics (ITWG) and other best practices. We are also investigating the validity of traditional forensic techniques (like fingerprints and DNA) on evidence contaminated with radioactive material alongside more novel parameters, e.g. the isotopic composition at the ‘bulk’ material and the micro scale using advanced micro-analytical techniques. We are moving towards the integration of a range of radio analytical techniques such as mass spectrometry, electron microscopy and the simulation/modelling of material production signatures, to provide a range of different information streams to assist attribution. With each advance in our technical competencies we enhance our means to ensure the security of nuclear or other radioactive material.
Calibration of the Capintec CRC-712M dose calibrator for 18F
(Elsevier, 2006-04) Mo, L; Reinhard, MI; Davies, JB; Alexiev, D; Baldock, C
Primary standardisation was performed on a solution of 18F using the 4πβ–γ coincidence counting efficiency-tracing extrapolation method with 60Co used as a tracer nuclide. The result was used to calibrate the ANSTO secondary standard ionisation chamber which is used to disseminate Australian activity standards for gamma emitters. Using the secondary activity standard for 18F, the Capintec CRC-712M dose calibrator at the Australian National Medical Cyclotron (NMC) Positron Emission Tomography (PET) Quality Control (QC) Section was calibrated. The dial setting number recommended by the manufacturer for the measurement of the activity of 18F is 439. In this work, the dial setting numbers for the activity measurement of the solution of 18F in Wheaton vials were experimentally determined to be 443±12, 446±12, 459±11, 473±15 for 0.1, 1, 4.5 and 9 ml solution volumes, respectively. The uncertainties given above are expanded uncertainties (k=2) giving an estimated level of confidence of 95%. The activities determined using the manufacturer recommended setting number 439 are 0.8%, 1.4%, 4.0% and 6.5% higher than the standardised activities, respectively. It is recommended that a single dial setting number of 459 determined for 4.5 ml is used for 0.1–9 ml solution in Wheaton vials in order to simplify the operation procedure. With this setting the expended uncertainty (k=2) in the activity readout from the Capintec dose calibrator would be less than 6.2%. © 2006, Elsevier Ltd.
Characterisation of a ΔE–E particle telescope using the ANSTO heavy ion microprobe
(Elsevier, 2007-07) Siegele, R; Reinhard, MI; Prokopovich, DA; Ionescu, M; Cohen, DD; Rosenfeld, AB; Cornelius, IM; Wroe, A; Lerch, MLF; Fazzi, A; Pola, A; Agosteo, S
Semiconductor planar processing technology has spurned the development of novel radiation detectors with applications in space, high energy physics, medical diagnostics, radiation protection and cancer therapy. The ANSTO heavy ion microprobe, which allows a wide range of ions to be focused into spot sizes of a few micrometers in diameter, has proven to be an essential tool for characterising these detectors using the Ion Beam Induced Charge (IBIC) imaging technique. The use of different ions and the wide range of available energies on the heavy ion microprobe, allows the testing of these devices with ionising particles associated with different values of linear energy transfer (LET). Quadruple coincidence measurements have been used to map the charge collection characteristics of a monolithic ΔE-E telescope, This was done through simultaneous measurement of the spatial coordinates of the microbeam relative to the sample and the response of both detector elements. The resulting charge collection maps were used to better understand the functionality of the device as well as to ascertain ways in which future device designs could be modified to improve performance. © 2007, Elsevier Ltd.
Characterisation of single-crystal mercuric iodide
(Elsevier, 2004-01-21) Alexiev, D; Dytlewski, N; Reinhard, MI; Mo, L
The mobility-lifetime product of electrons and holes in single-crystal mercuric iodide for detector applications was measured to be 4×10−5 and 3×10−5 cm2/V respectively. The charge carriers were optically induced by a near band gap excitation using a GaP (560 nm) light emitting diode. Optical Deep Level Transient Spectrometry measurements of trapping states showed three dominant energy levels at 0.26, 0.8 and 1.4 eV. There is little correlation between trapping levels reported in the literature. © 2004, Elsevier Ltd.
Charge transport properties of CdMnTe radiation detectors
(EDP Sciences, 2012-04-11) Rafiei, R; Boardman, DA; Reinhard, MI; Sarbutt, A; Kim, KH; Watt, GC; Uxa, S; Prokopovich, DA; Belas, E; Bolotnikov, AE; James, RB
Growth, fabrication and characterization of indium-doped cadmium manganese telluride (CdMnTe) radiation detectors have been described. Alpha-particle spectroscopy measurements and time resolved current transient measurements have yielded an average charge collection efficiency approaching 100 %. Spatially resolved charge collection efficiency maps have been produced for a range of detector bias voltages. Inhomogeneities in the charge transport of the CdMnTe crystals have been associated with chains of tellurium inclusions within the detector bulk. Further, it has been shown that the role of tellurium inclusions in degrading charge collection is reduced with increasing values of bias voltage. The electron drift velocity was calculated from the rise time distribution of the preamplifier output pulses at each measured bias. From the dependence of drift velocity on applied electric field the electron mobility was found to be μn = (718 ± 55) cm2/Vs at room temperature. © 2012 the Authors, published by EDP Sciences.
Comparison of SOI microdosimeter and tissue equivalent proportional counter measurements at the CERF facility
(Institute of Electrical and Electronics Engineers (IEEE), 2010-01-29) Prokopovich, DA; Reinhard, MI; Taylor, GC; Hands, A; Rosenfeld, AB
The CERN-EU High Energy Reference Field (CERF) facility is used in the calibration of neutron dosimeters for aviation and high energy physics applications. A comparison of the facility's microdosimetric spectra obtained with a new Silicon on Insulator (SOI) Microdosimeter and a HAWK Tissue Equivalent Proportional Counter (TEPC) are presented. Experimental measurements with a silicon PIN dosimeter diode are also described which indicate a small but significant contribution from charged particles to dosimetry measurements within the neutron dominated field.
Cylindrical silicon-on-insulator microdosimeter: charge collection characteristics.
(Australian Institute of Nuclear Science and Engineering (AINSE), 2007-11-22) Ziebell, AL; Lim, WH; Reinhard, MI; Cornelius, IM; Prokopovich, DA; Siegele, R; Dzurak, AS; Rosenfeld, AB
At present there exists a need, in both medical physics and radiation protection, for a portable microdosimeter that can be used in determining the radiobiological effectiveness (RBE) of different mixed radiation fields.
Cylindrical silicon-on-insulator microdosimeter: design, fabrication and TCAD modeling
(Institute of Electrical and Electronics Engineers (IEEE), 2009-04) Lim, WH; Ziebell, AL; Cornelius, IM; Reinhard, MI; Prokopovich, DA; Dzurak, AS; Rosenfeld, AB
A novel silicon-on-insulator (SOI) microdosimeter has been designed and fabricated using planar processing techniques to realise a device with a micron-scale well-defined sensitive volume. Cylindrical structures were employed to allow for an improved definition of the average chord length of the sensitive volume over that of previous elongated parallelepiped solid-state detector designs. The structures were manufactured on individual silicon mesas situated on top of a buried oxide insulating layer. The mesa design eliminated lateral charge diffusion. Two kinds of test structures were designed with sensitive region widths of 2 mum and 10 mum. In addition, an array of 900 cylindrical diodes was fabricated to increase the charge collection statistics. TCAD (Technology Computer Aided Design) modeling of the electrostatic potential and electric field profile of the cylindrical microdosimeter was carried out to obtain 3D potential and electric field profiles. The modeling revealed a radial electric field within the cylindrical-shaped sensitive volume with a 1/r dependence. While the electric field at the core of the cylindrical microdosimeter was not sufficiently high to induce avalanche signal multiplication, the higher electric field at the core should still assist in the measurement of low linear-energy transfer (LET) events. © 2009, Institute of Electrical and Electronics Engineers (IEEE)
The determination of the efficiency of a Compton suppressed high purity germanium detector using Monte Carlo simulations
(South Pacific Radioactivity Association, 2010-09-01) McNamara, AL; Heijnis, H; Fierro, D; Reinhard, MI
The low level radiochemistry laboratory at the Australian Nuclear Science and Technology Organisation (ANSTO) performs radioactivity measurements of various environmental samples for a broad range of low level radionuclides. The laboratory's low-level gamma-spectrometry facility contains two Compton suppressed high purity Germanium (HPGe) detector systems. A Compton suppressed HPGe detector is well suited to the analysis of small environmental samples, however the nature of these samples (range of different geometries, densities and compositions) can make it difficult to construct an efficiency curve for the instrument. Currently, efficiency calibrations are f, carried out using reference materials packed into a particular geometry, e.g. a petri-dish. This makes the analysis of samples with different geometries difficult and time-consuming. Monte Carlo simulations can be a powerful tool in estimating the efficiency of the detector, especially for complicated detector systems and unusual sample compositions and geometries, provided enough geometric information on the system is available. Monte Carlo radiation transport simulations can also be used to determine self absorption, random and coincidence summing corrections, cascade and background effects. We model the gamma-Compton suppressed system using the simulation toolkit Geant4 for the efficiency calibration and compare the calculated efficiencies with the measurement of standard radionuclides in the low energy region of ~ 40 to 1500 keV. The calculated I7 efficiencies have the same dependence on energy as the measured values and the discrepancies between the two values can be attributed to incomplete knowledge of the detector geometry.
The determination of the efficiency of a Compton suppressed HPGe detector using Monte Carlo simulations
(Elseiver, 2012-04-01) McNamara, AL; Heijnis, H; Fierro, D; Reinhard, MI
Compton suppressed high-purity germanium (HPGe) detector is well suited to the analysis of low levels of radioactivity in environmental samples. The difference in geometry, density and composition of environmental calibration standards (e.g. soil) can contribute to excessive experimental uncertainty to the measured efficiency curve. Furthermore multiple detectors, like those used in a Compton suppressed system, can add complexities to the calibration process. Monte Carlo simulations can be a powerful complement in calibrating these types of detector systems, provided enough physical information on the system is known. A full detector model using the Geant4 simulation toolkit is presented and the system is modelled in both the suppressed and unsuppressed mode of operation. The full energy peak efficiencies of radionuclides from a standard source sample is calculated and compared to experimental measurements. The experimental results agree relatively well with the simulated values (within similar to 5 - 20%). The simulations show that coincidence losses in the Compton suppression system can cause radionuclide specific effects on the detector efficiency, especially in the Compton suppressed mode of the detector. Additionally since low energy photons are more sensitive to small inaccuracies in the computational detector model than high energy photons, large discrepancies may occur at energies lower than similar to 100 keV. Crown Copyright (C) 2011 Published by Elsevier Ltd. All rights reserved.
Development and fabrication of cylindrical silicon-on-insulator microdosimeter arrays.
(Institute of Electrical and Electronics Engineers (IEEE), 2009-06) Lai, NS; Lim, WH; Ziebell, AL; Reinhard, MI; Rosenfeld, AB; Dzurak, AS
Recent developments in the fabrication and simulation of prototype silicon-on-insulator (SOI) microdosimeter arrays are presented. A new planar array design has been proposed which has a number of advantages over the previous elongated parallelepiped and cylindrical mesa array designs. This novel planar array design, which incorporates a guard ring, is based upon 2500 planar cylindrically shaped p-i-n detectors and was fabricated via dopant diffusion and ion implantation. The dopant-diffused arrays were successfully fabricated and tested using 2 mum and 10-mum- thick SOI substrates. Technology computer-aided design modeling of the ion-implanted structure is presented which includes the electrostatic potential profile, showing possible avalanche signal multiplication around the n+ core of the microdosimeter. The alpha particle charge transient response was simulated to determine the charge collection in the sensitive region. © 2009, Institute of Electrical and Electronics Engineers (IEEE)
Development of a large-area silicon α-particle detector
(Elsevier, 2014-09) Tran, LT; Prokopovich, DA; Lerch, MLF; Petasecca, M; Siegele, R; Reinhard, MI; Perevertaylo, VL; Rosenfeld, AB
Circular ion-implanted silicon detector of α-particles with a large, 5-cm2, sensitive area has been developed. An advantage of the detector is that the detector surface is easily cleanable with chemicals. The hardened surface of the detector shows no signs of deterioration of the spectroscopic and electrical characteristics upon repeated cleaning. The energy resolution along the diameters of the detector was (1.0±0.1)% for the 5.486-MeV α-particles. Detailed tests of the charge collection efficiency and uniformity of the detector entrance window were also performed with a 5.5-MeV He2+ microbeam. © 2014, Elsevier Ltd.
Development of the Australian standard for germanium-68 by two liquid scintillation counting methods
(Elsevier B. V., 2018-04) van Wyngaardt, WM; Smith, ML; Jackson, TW; Howe, B; Tobin, SM; Reinhard, MI
In response to the increasing application of 68Ge/68Ga and 68Ga in nuclear medicine, an international comparison of activity measurement of 68Ge in equilibrium with 68Ga was organised. ANSTO standardised the comparison solution by the 4π(LS)β+-γ coincidence extrapolation and TDCR efficiency calculation methods, with excellent agreement between the two results. The primary standard was transferred to the ANSTO Secondary Standard Ionisation Chamber. Internationally traceable Australian Certified Reference Materials (ACRMs) of 68Ge/68Ga can now be prepared in various measurement geometries applied in nuclear medicine. © 2017 Crown Copyright, Published by Elsevier Ltd. All
Evaluation of silicon detectors with integrated JFET for biomedical applications
(Institute of Electrical and Electronics Engineers (IEEE), 2009-06) Safavi-Naeini, M; Franklin, DR; Lerch, MLF; Petasecca, M; Pignatel, G; Reinhard, MI; Dalla Betta, GF; Zorzi, N; Rosenfeld, AB
This paper presents initial results from electrical, spectroscopic and ion beam induced charge (IBIC) characterisation of a novel silicon PIN detector, featuring an on-chip n -channel JFET and matched feedback capacitor integrated on its p-side (frontside). This structure reduces electronic noise by minimising stray capacitance and enables highly efficient optical coupling between the detector back-side and scintillator, providing a fill factor of close to 100%. The detector is specifically designed for use in high resolution gamma cameras, where a pixellated scintillator crystal is directly coupled to an array of silicon photodetectors. The on-chip JFET is matched with the photodiode capacitance and forms the input stage of an external charge sensitive preamplifier (CSA). The integrated monolithic feedback capacitor eliminates the need for an external feedback capacitor in the external electronic readout circuit, improving the system performance by eliminating uncontrolled parasitic capacitances. An optimised noise figure of 152 electrons RMS was obtained with a shaping time of 2 mus and a total detector capacitance of 2 pF. The energy resolution obtained at room temperature (2°C) at 27 keV (direct interaction of I-125 gamma rays) was 5.09%, measured at full width at half maximum (FWHM). The effectiveness of the guard ring in minimising the detector leakage current and its influence on the total charge collection volume is clearly demonstrated by the IBIC images. © 2009, Institute of Electrical and Electronics Engineers (IEEE)
Evidence against solar influence on nuclear decay constants
(Elsevier B. V., 2016-10-10) Pommé, S; Stroh, H; Paepen, J; Van Ammel, R; Marouli, M; Altzitzoglou, T; Hult, M; Kossert, K; Nähle, O; Schrader, H; Juget, F; Bailat, CJ; Nedjadi, Y; Bochud, F; Buchillier, T; Michotte, C; Courte, S; van Rooy, MW; van Staden, MJ; Lubbe, J; Simpson, BRS; Fazio, A; De Felice, P; Jackson, TW; van Wyngaardt, WM; Reinhard, MI; Golya, J; Bourke, S; Roy, T; Galea, R; Keightley, JD; Ferreira, KM; Collins, SM; Ceccatelli, A; Unterweger, MP; Fitzgerald, R; Bergeron, DE; Pibida, L; Verheyen, L; Bruggeman, M; Vodenik, B; Korun, M; Chisté, V; Amiot, MN
The hypothesis that proximity to the Sun causes variation of decay constants at permille level has been tested and disproved. Repeated activity measurements of mono-radionuclide sources were performed over periods from 200 days up to four decades at 14 laboratories across the globe. Residuals from the exponential nuclear decay curves were inspected for annual oscillations. Systematic deviations from a purely exponential decay curve differ from one data set to another and are attributable to instabilities in the instrumentation and measurement conditions. The most stable activity measurements of alpha, beta-minus, electron capture, and beta-plus decaying sources set an upper limit of 0.0006% to 0.008% to the amplitude of annual oscillations in the decay rate. Oscillations in phase with Earth's orbital distance to the Sun could not be observed within a to range of precision. There are also no apparent modulations over periods of weeks or months. Consequently, there is no indication of a natural impediment against sub-permille accuracy in half-life determinations, renormalisation of activity to a distant reference date, application of nuclear dating for archaeology, geo- and cosmochronology, nor in establishing the SI unit becquerel and seeking international equivalence of activity standards. © 2016 The Authors. Published by Elsevier B.V.
From imaging to dosimetry: GEANT4-based study on the application of medipix to neutron dosimetry
(Elsevier, 2009-10-12) Othman, MAR; Marinaro, DG; Petasecca, M; Guatelli, S; Cutajar, DL; Lerch, MLF; Prokopovich, DA; Reinhard, MI; Uher, J; Jakubek, J; Pospisil, S; Rosenfeld, AB
An application of Medipix2 using a newly developed segmented multiple thickness polyethylene (PE) converter for fast neutron detection is presented. The system has the ability to provide an energy independent response for the dose equivalent for fast neutrons. The application of weighting factors to each defined thickness of PE allows for a flattening of the response of the detector system for dosimetry applications. Six PE converter segments were applied, and their thicknesses and weighting factors were optimised to obtain the required energy independent detector response. The study performed by means of GEANT4. Its suitability for neutron dosimetry was studied with respect to a previously published work. © 2013 Elsevier B.V.
Geant4 simulation of the CERN-EU high-energy reference field (CERF) facility
(Oxford University Press (OUP), 2010-09) Prokopovich, DA; Reinhard, MI; Cornelius, IM; Rosenfeld, AB
The CERN-EU high-energy reference field facility is used for testing and calibrating both active and passive radiation dosemeters for radiation protection applications in space and aviation. Through a combination of a primary particle beam, target and a suitable designed shielding configuration, the facility is able to reproduce the neutron component of the high altitude radiation field relevant to the jet aviation industry. Simulations of the facility using the GEANT4 (GEometry ANd Tracking) toolkit provide an improved understanding of the neutron particle fluence as well as the particle fluence of other radiation components present. The secondary particle fluence as a function of the primary particle fluence incident on the target and the associated dose equivalent rates were determined at the 20 designated irradiation positions available at the facility. Comparisons of the simulated results with previously published simulations obtained using the FLUKA Monte Carlo code, as well as with experimental results of the neutron fluence obtained with a Bonner sphere spectrometer, are made. © 2010, Oxford University Press (OUP)

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