The FastScan whole body counter: efficiency as a function of BOMAB phantom size and energy modelled by MCNP
|
|
- Gerard Green
- 5 years ago
- Views:
Transcription
1 The FastScan whole body counter: efficiency as a function of BOMAB phantom size and energy modelled by MCNP Gary H. Kramer and Jeannie Fung Human Monitoring Laboratory, Radiation Protection Bureau, 775 Brookfield Road, Ottawa, Ontario K1A 1C1, Canada (gary_h_kramer@hc-sc.gc.ca, Abstract. The Canberra FastScan whole body counter has been investigated using Monte Carlo simulations. In this manner, the counter has been virtually calibrated using detectors and phantoms of different sizes. The results have been compared with the five FastScan counters currently deployed in different locations throughout Canada. The results show that when a person is measured in a FastScan, and their body size is different from that of the Reference Man calibration phantom, the error introduced into the activity estimate is small with a maximum value of about 10%, either as an over- or under-estimate. If the two smaller phantoms are ignored (the four and ten year old) then the size dependency remains at about 10%, but only as an overestimate. The results also shows that the current commercial version of the FastScan counter has the best counting efficiency of the three system simulated up to 1173 kev. 1.0 Introduction There are five FastScan whole body counters in Canada. Their performance characteristics were reported elsewhere [1] and it was apparent that these instruments seemed to suffer less size dependency than other types of whole body counters (i.e., chair, bed, scanning bed). To further investigate this phenomenon, the FastScan whole body counter was modelled and its counting efficiency simulated for a variety of BOMAB phantom sizes using MCNP4A. The use of Monte Carlo simulations to establish calibration data has several advantages as the purchase of a BOMAB phantom family can be both expensive and its use time consuming. The establishment of all the calibration curves for a FastScan whole body counter would require the HML to: purchase radioactive standards that cover the required energy range (100-2,000 kev), fill each phantom with a single radionuclide, visit one of the FastScan sites for a long enough period to perform all the calibrations (this would be problematic as they are in routine and continual use at the Canadian Power Generating Stations), develop the calibration sets. The work would take several weeks to cover all the phantom sizes and photon energies and would create many litres of radioactive waste. The alternative, Monte Carlo simulations, suffers from none of the above disadvantages. 2.0 Methods and Materials 2.1 Modelling of the BOMAB phantoms: The HML uses BOMAB phantoms that simulate: A Reference four year old child (P4), a Reference ten year old child (P10), a five-percentile male (PM5), a Reference Female (PF), Reference Male (PM), and a 95-percentile male (PM95). The Reference phantoms (P4, P10, PF, and PM) were originally developed from data contained in Reference Man [2]. The other phantoms (PM5 and PM95) were designed using selected anthropometry data [3] (Nutrition Canada 1980). The phantoms were measured in the HML to determine the height, semi-major, and semi-minor axis of each phantom. The thickness of the high density polyethylene wall was 0.25 cm except at the filling cap end where it was 1.5 cm. This data was used to construct a set of virtual BOMAB phantoms. 2.2 The FastScan Counter: The FastScan uses two NaI (Tl) detectors, configured in a linear array on a common vertical axis. Originally the detectors were each 10.2 cm x 10.2 cm x 40.6 cm with a single photo-multiplier tube at the end; a later design changed the detector to 7.6 cm x 12.7 cm x 40.6 cm. 1
2 The subject stands inside the shield facing the detectors. The detectors are shielded by 10 cm of low background steel and the whole unit weighs 4,500 kg. The counter occupies floor space of only 1.3 m x 1 m, and is less than 2.1 m in height. The vertical detector placement and interior shield dimensions were chosen based upon anthropometric data of a working population [4] of both adult males and females. The locations of the internal organs were obtained from the Synder-MIRD Mathematical Phantom [5]. Canberra supplied some more detailed diagrams of detector locations, and shield composition so that the FastScan could be modelled. This information was used to model the detectors, local shielding and support structure. Three sizes of detectors were modelled: 10.2 cm x 10.2 cm x 40.6 cm, 7.6 cm x 12.7 cm x 40.6 cm., and 10.2 cm x 12.7 cm x 40.6 cm (width, depth and height respectively). The photomultiplier tubes were not modelled. For ease of identification in the discussion below, the three counting systems will be labelled as System 1, System 2, and System 3, respectively. 2.3 The Simulations: The following energies were simulated: 126, 280, 364, 468, 662, 834, 1173, 1332, 1460, 1836 and 2754 kev. Many of these photon energies were chosen to represent radionuclides frequently used in calibrations: 57 Co, 131 I, 137 Cs, 60 Co, 54 Mn, 40 K, 88 Y, 24 Na. The remaining energies are interpolations to fill in areas so that efficiency versus energy curves can be constructed. Each photon energy was run independently and were mono-energetic for each phantom size. The photons that interacted with the upper and lower detectors and deposited their full energy were tallied so that a detector efficiency was obtained for the upper detector and lower detector. The array (upper and lower combined) efficiency was obtained simply by summing the two detectors. The Monte Carlo code used for the simulations has been described in detail elsewhere [6]. The authors of MCNP consider that a relative error value of suggests that the tally result is questionable [7]. Tally results for which the relative error is above 0.2 are not likely to be meaningful, but are generally reliable for a relative error less than 0.1. The number of photons used in the simulations was 10 7 so that the relative error varied from to for the lower detector and to for the upper detector. 2.4 Benchmarking: The five Canadian facilities that own and operate a FastScan whole body counter supplied their efficiency data to the HML in the form of efficiency equations. The form of the efficiency equations in use are: Pt Lepreau: 2 3 ( a2+ a3. x+ a4. x + a5. x ) Eff= e and x = Ln( a1 / energy) Other stations: ( b1+ b2. y+ b3. y + b4 y + b5 y + b6 y ) Eff= e and y = Ln( energy) where a1' to a5' and b1' to b6' are regression coefficients determined from the Canberra software. 3.0 Results and Discussion 3.1 Counting Efficiency: The counting efficiencies of the virtual BOMAB phantoms as a function of photon energy are shown in Tables 1-9. The tables give efficiencies for the upper detector, lower detector, and detector array for each of the simulated detector sizes (Systems 1-3). 2
3 Table 1: Counting efficiency (count/photon) of the upper detector (System 3) of a FastScan WBC using different sized virtual BOMAB phantoms as a function of photon energy. P4 = four year old phantom, P10 = 10 year old phantom, PM5 = five percentile phantom, PF = female phantom, PM = male phantom, PM95 = ninety fifth percentile phantom. P x x x x x x 10-4 P x x x x x x 10-3 PM x x x x x x 10-3 PF 2.21 x x x x x x 10-3 PM 2.44 x x x x x x 10-3 PM x x x x x x 10-3 P x x x x x 10-4 P x x x x x 10-3 PM x x x x x 10-3 PF 2.09 x x x x x 10-3 PM 2.36 x x x x x 10-3 PM x x x x x 10-3 Table 2: Counting efficiency (count/photon) of the lower detector (System 3) of a FastScan WBC using different sized virtual BOMAB phantoms as a function of photon energy. P x x x x x x 10-3 P x x x x x x 10-3 PM x x x x x x 10-3 PF 4.04 x x x x x x 10-3 PM 3.49 x x x x x x 10-3 PM x x x x x x 10-3 P x x x x x 10-3 P x x x x x 10-3 PM x x x x x 10-3 PF 3.81 x x x x x 10-3 PM 3.44 x x x x x 10-3 PM x x x x x 10-3 Table 3: Counting efficiency (count/photon) of the detector array (System 3) of a FastScan WBC using different sized virtual BOMAB phantoms as a function of photon energy. 126 kev 280 kev 364 kev 468 kev 662 kev 834 kev P x x x x x x 10-3 P x x x x x x 10-3 PM x x x x x x 10-3 PF 6.25 x x x x x x 10-3 PM 5.94 x x x x x x 10-3 PM x x x x x x 10-3 P x x x x x 10-3 P x x x x x 10-3 PM x x x x x 10-3 PF 5.90 x x x x x 10-3 PM 5.80 x x x x x 10-3 PM x x x x x
4 Table 4: Counting efficiency (count/photon) of the upper detector (System 2) of a FastScan WBC using different sized virtual BOMAB phantoms as a function of photon energy. P x x x x x x 10-4 P x x x x x x 10-3 PM x x x x x x 10-3 PF 2.51 x x x x x x 10-3 PM 2.84 x x x x x x 10-3 PM x x x x x x 10-3 P x x x x x 10-4 P x x x x x 10-4 PM x x x x x 10-3 PF 1.94 x x x x x 10-3 PM 2.24 x x x x x 10-3 PM x x x x x 10-3 Table 5: Counting efficiency (count/photon) of the lower detector (System 2) of a FastScan WBC using different sized virtual BOMAB phantoms as a function of photon energy. P x x x x x x 10-3 P x x x x x x 10-3 PM x x x x x x 10-3 PF 4.93 x x x x x x 10-3 PM 4.25 x x x x x x 10-3 PM x x x x x x 10-3 P x x x x x 10-3 P x x x x x 10-3 PM x x x x x 10-3 PF 3.92 x x x x x 10-3 PM 3.54 x x x x x 10-3 PM x x x x x 10-3 Table 6: Counting efficiency (count/photon) of the detector array (System 2) of a FastScan WBC using different sized virtual BOMAB phantoms as a function of photon energy. 126 kev 280 kev 364 kev 468 kev 662 kev 834 kev P x x x x x x 10-3 P x x x x x x 10-3 PM x x x x x x 10-3 PF 7.44 x x x x x x 10-3 PM 7.09 x x x x x x 10-3 PM x x x x x x 10-3 P x x x x x 10-3 P x x x x x 10-3 PM x x x x x 10-3 PF 5.87 x x x x x 10-3 PM 5.78 x x x x x 10-3 PM x x x x x
5 Table 7: Counting efficiency (count/photon) of the upper detector (System 1) of a FastScan WBC using different sized virtual BOMAB phantoms as a function of photon energy. P x x x x x x 10-4 P x x x x x x 10-3 PM x x x x x x 10-3 PF 2.13 x x x x x x 10-3 PM 2.38 x x x x x x 10-3 PM x x x x x x 10-3 P x x x x x 10-4 P x x x x x 10-4 PM x x x x x 10-3 PF 1.84 x x x x x 10-3 PM 2.11 x x x x x 10-3 PM x x x x x 10-3 Table 8: Counting efficiency (count/photon) of the lower detector (System 1) of a FastScan WBC using different sized virtual BOMAB phantoms as a function of photon energy. P x x x x x x 10-3 P x x x x x x 10-3 PM x x x x x x 10-3 PF 4.13 x x x x x x 10-3 PM 3.57 x x x x x x 10-3 PM x x x x x x 10-3 P x x x x x 10-3 P x x x x x 10-3 PM x x x x x 10-3 PF 3.60 x x x x x 10-3 PM 3.26 x x x x x 10-3 PM x x x x x 10-3 Table 9: Counting efficiency (count/photon) of the detector array (System 1) of a FastScan WBC using different sized virtual BOMAB phantoms as a function of photon energy. 126 kev 280 kev 364 kev 468 kev 662 kev 834 kev P x x x x x x 10-3 P x x x x x x 10-3 PM x x x x x x 10-3 PF 6.25 x x x x x x 10-3 PM 5.95 x x x x x x 10-3 PM x x x x x x 10-3 P x x x x x 10-3 P x x x x x 10-3 PM x x x x x 10-3 PF 5.44 x x x x x 10-3 PM 5.36 x x x x x 10-3 PM x x x x x
6 Eff (cnt/photon) The differences between the three crystal sizes are shown in Fig. 1 using the PM phantom. Other phantoms gave similar results to Fig. 1. At low energies Systems 1 and 3 perform identically. As the energy rises the efficiency of System 3 rises above that of System 1 due to the greater thickness of the detector crystal. System 2 has the highest efficiency at low energies due to the increased width of the crystal compared with the other systems. Its counting efficiency falls below that of System 3 at about 1200 kev but remains above System 1 over the range simulated (126 kev kev). This indicates 0.01 System 1 System 2 System Fig 1: Efficiency of the PM BOMAB phantom as a function of photon energy for three detector crystal sizes. that of the three systems System 2 is the best choice in terms of counting efficiency for expected nuclides. The upper and lower detector are both geometry dependent as can be seen from Tables 1-9. The smallest phantom, P4, has the highest counting efficiency when measured by the lower detector whereas the largest phantom, PM95, has similar efficiencies in both upper and lower detectors. Fortunately, when the two detectors are summed to give a two-detector array the counting efficiencies are almost independent of phantom size. The biggest difference would be between the P4 and PM95 phantoms and for the lower, upper and array these differences at 126 kev are a factor of 0.54, 3.4, and 0.90, respectively. The size dependency of System 2 is illustrated in Fig. 2 where it can be seen that the counting efficiency of the smaller phantoms drops below that of the bigger phantoms as the energy (kev)
7 Eff (cnt/photon) 0.01 P4 P10 PM PF PM PM (kev) Fig. 2: Counting Efficiency of all the phantoms in System 2. rises. For example, the P4 phantom becomes less efficient than the PM95 phantom at energies > 468 kev. This is likely due to the lessening importance of self-attenuation of the emitted photons by the stable components of the phantoms. 3.2 Minimum Detectable Activity: Background is proportional to detector volume [8]. The larger the volume the larger the background. The volumes of Systems 1-3 are: 4182 cm 3, 3880 cm 3, 5207 cm 3, respectively. System 2, therefore, is the best choice as the background would be expected to be the lowest and the efficiency is the highest. 3.3 Benchmarking: The regression parameters that describe the FastScan efficiency equations are given in Table 10. The efficiency equations are also shown in Fig. 3 where it can be seen that four of the five agree quite well while the fifth exhibits lower efficiencies. The latter whole body counter is of the first generation and has smaller detectors than the other four. The disagreement of the counting efficiencies of the remaining four counting systems in the lower energy range is due to the different facilities choice of fitting algorithm - see above and Table 10.The efficiency equations were developed using the Canberra Transfer Phantom (CTF) and standard sources. The CTF can simulate a lung, GI, whole body, or thyroid geometry and is easy to use because it requires no assembly and uses a single source in a 20 ml liquid scintillation vial for all calibration geometries. The manufacturer states that this phantom is not appropriate for low energy measurements, or geometries where the detector is behind the subject, or for counters other than Canberra linear geometry counters. 7
8 Eff (cnt/photon) Table 10: Regression parameters for the FastScan efficiency equations. Facility Regression parameter a1 a2 a3 a4 a5 Pt Lepreau b1 b2 b3 b4 b5 b6 Pickering Darlington Bruce A Bruce B Pickering (new detectors) Pt Lepreau Pickering Darlington Bruce A Bruce B Pick. New Det (kev) Fig. 3: Plot of the five Canadian FastScan whole body counters. The efficiency response with this phantom has been designed to replicate the ANSI N13.30 phantoms (Livermore Lung, BOMAB total body and ANSI-N-44.3 Thyroid) for the Canberra counters; however, the simulations have been performed with BOMAB phantoms. Fig. 4 shows the Reference Man BOMAB counting efficiencies compared to the Hydro One FastScan counters. The agreement is excellent considering the scatter in the observed data. The Pt Lepreau data has been omitted. 8
9 CE(cnt/photon) 3.4 Size Dependency: Over the energies and phantom sizes simulated the size dependency of System 2 is found to be between 0.92 and 1.10 of the counting efficiency of the PM phantom (RefMan). Systems 1 and 3 perform similarly. This means that when a person is measured in a FastScan, and their body size is different from that of the Reference Man calibration phantom, the error introduced into the activity estimate is small with a maximum value of about 10%, either as an over- or underestimate. If the two smaller phantoms are ignored (the four and ten year old) then the size dependency remains at about 10%, but only as an overestimate. Looking more closely at the data in Table 6 one sees that the counting efficiency of the PM phantom is 0.01 System 2 Pickering Darlington Bruce B Bruce A (kev) Fig. 4: Comparison of measured and predicted efficiency curves for the FastScan Whole Body Counter using the PM phantom (RefMan). the lowest of the series PM5, PF, PM, and PM95 (except at 126 kev) indicating that any deviation from the Reference Man size will lead to an over-estimate of the body burden and, therefore, an overestimate of the dose estimate. This finding suggests that the FastScan should be calibrated using a phantom that is representative of the median (height, weight) of the population being measured to avoid biasing the whole body counting results. 9
10 4.0 Conclusions The response of the FastScan has been modelled with three detector sizes, including the one currently sold by Canberra. The results have also been compared to the efficiency data of the five FastScan counters currently in use across Canada to validate the results of the modelling. The results show that Monte Carlo can be used to perform a primary calibration that would otherwise be both expensive and difficult. 5.0 Acknowledgements The Human Monitoring Laboratory wishes to thank the FastScan operators at Pt. Lepreau NGS, Darlington NGS, Pickering NGS and the Bruce NGS for supplying the efficiency data used in this report. References 1. Kramer GH. Performance Testing of the Canberra FastScan Whole Body Counters in Canada. Rad. Prot. Manag. 17(1): 31-38, (2000). 2. International Commission on Radiological Protection. Report of the Task Group on Reference Man. Oxford: Pergamon Press; ICRP Publication 23, (1975). 3. Nutrition Canada. Anthropometry Report: Height, Weight and Body Dimensions. Ottawa: Health and Welfare Canada, (1980). 4. Panero J, Zelnick M. Human Dimension and Interior Space. Whitney Library of Design, New York, (1979). 5. Snyder WS, Ford MR, Warner GG, Fisher HL. Estimates of absorbed fractions for monoenergetic photon sources uniformly distributed in various organs of a heterogeneous phantom. J Nucl Med Sup No. 3: 7-52, (1969). 6. Kramer GH, Burns LC, Guerriere S. Monte Carlo simulation of a scanning detector whole body counter and the effect of BOMAB phantom size on the calibration. Health Phys 83(4): , (2002). 7. Briesmeister JF. MCNP - A general Monte Carlo code for neutron and photon transport. Los Alamos, NM: Los Alamos National Laboratory; LA-7396-M, Rev. 2, (1986). 8. Keyser RM, Wagner S. Using the IEC standard to describe low-background detectors - what may one expect. Proceedings of the winter meeting of the American Nuclear Society, Washington DC, (1998). 10
Intercomparison of JAERI Torso Phantom lung sets
Intercomparison of JAERI Torso Phantom lung sets Gary H. Kramer and Barry M. Hauck Human Monitoring Laboratory, Radiation Protection Bureau, 775 Brookfield Road, Ottawa, Ontario K1A 1C1 Canada (Gary_H_Kramer@hc-sc.gc.ca,
More informationJRPR. An Intercomparison of Counting Efficiency and the Performance of Two Whole-Body Counters According to the Type of Phantom.
Journal of Radiation Protection and Research 2016;41(3):274-281 pissn 2508-1888 eissn 2466-2461 An Intercomparison of Counting Efficiency and the Performance of Two Whole-Body Counters According to the
More informationRecent Activities on Neutron Standardization at the Electrotechnical Laboratory
Recent Activities on Neutron Standardization at the Electrotechnical Laboratory K. Kudo, N. Takeda, S. Koshikawa and A. Uritani Quantum Radiation Division, National Metrology Institute of Japan (NMIJ)
More informationRinghals AB. Routines for whole body counting at Ringhals NPP
Routines for whole body counting at Ringhals NPP Structure Equipment - Quick Scan - Whole body counter Marie Carlson M.Sc. Radiology and Dosimetry Radiation Physicist and deputy RP Controller Routines
More informationMonte Carlo Calculations Using MCNP4B for an Optimal Shielding Design. of a 14-MeV Neutron Source * James C. Liu and Tony T. Ng
SLAC-PUB-7785 November, 1998 Monte Carlo Calculations Using MCNP4B for an Optimal Shielding Design of a 14-MeV Neutron Source * James C. Liu and Tony T. Ng Stanford Linear Accelerator Center MS 48, P.O.
More informationInvestigation of Uncertainty Sources in the Determination of Gamma Emitting Radionuclides in the WBC
Investigation of Uncertainty Sources in the Determination of Gamma Emitting Radionuclides in the WBC A. Specification Whole body counting method is used to detect the gamma rays emitted by radio nuclides,
More informationDesign of a virtual model of a hand-held Germanium detector and a voxelized ICRP whole body phantom: A Monte Carlo study
Design of a virtual model of a hand-held Germanium detector and a voxelized ICRP whole body phantom: A Monte Carlo study ASM SABBIR AHMED 1, Gary H Kramer 2, Kurt Ungar 2 1 University of Saskatchewan,
More informationOrgan and effective dose rate coefficients for submersion exposure in occupational settings
Radiat Environ Biophys (2017) 56:453 462 DOI 10.1007/s00411-017-0705-6 ORIGINAL ARTICLE Organ and effective dose rate coefficients for submersion exposure in occupational settings K. G. Veinot 1,2 S. A.
More informationSensitivity of the IRD whole-body counter for in vivo measurements in the case of accidental intakes
Sensitivity of the IRD whole-body counter for in vivo measurements in the case of accidental intakes B.M. Dantas, E.A. Lucena and A.L.A. Dantas Laboratório de Monitoração In Vivo Divisão de Dosimetria
More informationAn Experimental Study of the Relative Response of Plastic Scintillators to Photons and Beta Particles
An Experimental Study of the Relative Response of Plastic Scintillators to Photons and Beta Particles 1) A Kumar 1 and A.J. Waker 1 Faculty of Energy System and Nuclear Science, UOIT, 2000 Simcoe St. N,
More informationCharacterization of the 3 MeV Neutron Field for the Monoenergetic Fast Neutron Fluence Standard at the National Metrology Institute of Japan
Characterization of the 3 MeV Neutron Field for the Monoenergetic Fast Neutron Fluence Standard at the National Metrology Institute of Japan Hideki Harano * National Metrology Institute of Japan, National
More informationAm-241 as a Metabolic Tracer for Inhaled Pu Nitrate in External Chest Counting
Am-24 as a Metabolic Tracer for Inhaled Pu Nitrate in External Chest Counting Nobuhito ISHIGURE, Takashi NAKANO, Hiroko ENOMOTO, Akira KOIZUMI, Harozo IIDA, Kumiko FUKUTSU, Yumi ABE 2, Yuji YAMADA, Katsuhiro
More information1 cm. Cu electrode. Ge crystal. end cap. Dead layer. crystal cup
Proceedings of the Ninth EGS4 Users' Meeting in Japan, KEK Proceedings 2001-22, p.30-36 APPLICATION OF Ge SEMI-CONDUCTOR DETECTOR TO WHOLE-BODY COUNTER S. Kinase 1 2, H. Noguchi 1 and T. Nakamura 2 1 Japan
More informationNeutron Dose near Spent Nuclear Fuel and HAW after the 2007 ICRP Recommendations
Neutron Dose near Spent Nuclear Fuel and HAW after the 2007 ICRP Recommendations Gunter Pretzsch Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbh Radiation and Environmental Protection Division
More informationWM2013 Conference, February 24 28, 2013, Phoenix, Arizona, USA
Testing and Performance Validation of a Sensitive Gamma Ray Camera Designed for Radiation Detection and Decommissioning Measurements in Nuclear Facilities- 13044 John A. Mason*, Richard Creed**, Marc R.
More informationMonte Carlo simulation for the estimation of iron in human whole blood and comparison with experimental data
Pramana J. Phys. (2017) 88: 49 DOI 10.1007/s12043-016-1344-1 c Indian Academy of Sciences Monte Carlo simulation for the estimation of iron in human whole blood and comparison with experimental data M
More informationCalibration of a Whole Body Counter and In Vivo measurements for Internal Dosimetry Evaluation in Chile, Two years experience.
Calibration of a Whole Body Counter and In Vivo measurements for Internal Dosimetry Evaluation in Chile, Two years experience. Osvaldo Piñones O., Sylvia Sanhueza M. Radio medicine Section, Chilean Commission
More informationDetection efficiency of a BEGe detector using the Monte Carlo method and a comparison to other calibration methods. Abstract
Detection efficiency of a BEGe detector using the Monte Carlo method and a comparison to other calibration methods N. Stefanakis 1 1 GMA Gamma measurements and analyses e.k. PO Box 1611, 72706 Reutlingen,
More informationNeutron Skyshine Calculations with the Integral Line-Beam Method
NUCLEAR SCIENCE AND ENGINEERING: 127, 230 237 ~1997! Technical Note Neutron Skyshine Calculations with the Integral Line-Beam Method Ah Auu Gui, J. Kenneth Shultis,* and Richard E. Faw Kansas State University,
More informationActivities of the neutron standardization. at the Korea Research Institute of Standards and Science (KRISS)
Activities of the neutron standardization at the Korea Research Institute of Standards and Science (KRISS) I. Introduction The activities of neutron standardization in KRISS have been continued for last
More informationRecent Activities on Neutron Calibration Fields at FRS of JAERI
Recent Activities on Neutron Calibration Fields at FRS of JAERI Michio Yoshizawa, Yoshihiko Tanimura, Jun Saegusa and Makoto Yoshida Department of Health Physics, Japan Atomic Energy Research Institute
More informationEvaluation of the Nonlinear Response Function and Efficiency of a Scintillation Detector Using Monte Carlo and Analytical Methods
Asian J. Exp. Sci., Vol. 28, No. 2, 2014; 23-31 Evaluation of the Nonlinear Response Function and Efficiency of a Scintillation Detector Using Monte Carlo and Analytical Methods Rahim Khabaz, Farhad Yaghobi
More informationQuality Assurance. Purity control. Polycrystalline Ingots
Quality Assurance Purity control Polycrystalline Ingots 1 Gamma Spectrometry Nuclide Identification Detection of Impurity Traces 1.1 Nuclides Notation: Atomic Mass Atomic Number Element Neutron Atomic
More informationCURRENT CAPABILITIES OF THE IRD-CNEN WHOLE BODY COUNTER FOR IN VIVO MONITORING OF INTERNALLY DEPOSITED RADIONUCLIDES IN HUMAN BODY
International Joint Conference RADIO 2014 Gramado, RS, Brazil, Augustl 26-29, 2014 SOCIEDADE BRASILEIRA DE PROTEÇÃO RADIOLÓGICA - SBPR CURRENT CAPABILITIES OF THE IRD-CNEN WHOLE BODY COUNTER FOR IN VIVO
More informationGamma-Spectrum Generator
1st Advanced Training Course ITCM with NUCLEONICA, Karlsruhe, Germany, 22-24 April, 2009 1 Gamma-Spectrum Generator A.N. Berlizov ITU - Institute for Transuranium Elements Karlsruhe - Germany http://itu.jrc.ec.europa.eu/
More informationGamma Analyst Performance Characteristics (MDAs)
Application Note Gamma Analyst Performance Characteristics (MDAs) Introduction With so much attention being given to environmental issues, the process of sample characterization is challenging today s
More informationA Radiation Monitoring System With Capability of Gamma Imaging and Estimation of Exposure Dose Rate
IEEE TRANSACTIONS ON NUCLEAR SCIENCE, VOL. 49, NO. 3, JUNE 2002 1547 A Radiation Monitoring System With Capability of Gamma Imaging and Estimation of Exposure Dose Rate Wanno Lee, Gyuseong Cho, and Ho
More informationEnergy Response Characteristics of Several Neutron Measuring Devices Determined By Using the Scattered Neutron Calibration Fields of KAERI
Energy Response Characteristics of Several Neutron Measuring Devices Determined By Using the Scattered Neutron Calibration s of KAERI B.H. Kim 1, J.L. Kim 1, S.Y. Chang 1, J.K. Chang 1, G. Cho 2 1 Korea
More informationPortal Monitor Characterization for Internally and Externally Deposited Radionuclides
Operational Topic Detection efficiencies for internally and externally deposited radionuclides have been evaluated using a pass-through and static mode portal monitor. Portal Monitor Characterization for
More informationProgress in Nuclear Science and Technology, Volume 6,
DOI: 1.15669/pnst.6 Progress in Nuclear Science and Technology Volume 6 (19) pp. 1-16 ARTICLE A study on calculation method of duct streaming from medical linac rooms Takuma Noto * Kazuaki Kosako and Takashi
More informationA New Anthropometric Calibration Phantom for In Vivo Measurement of Bone Seeking Radionuclides
A New Anthropometric Calibration Phantom for In Vivo Measurement of Bone Seeking Radionuclides H. B. Spitz and J. C.Lodwick University of Cincinnati, Department of Mechanical, Industrial & Nuclear Engineering,
More informationHigh Energy Neutron Scattering Benchmark of Monte Carlo Computations
International Conference on Mathematics, Computational Methods & Reactor Physics (M&C 2009) Saratoga Springs, New York, May 3-7, 2009, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2009) High
More informationDETERMINATION OF CORRECTION FACTORS RELATED TO THE MANGANESE SULPHATE BATH TECHNIQUE
DETERMINATION OF CORRECTION FACTORS RELATED TO THE MANGANESE SULPHATE BATH TECHNIQUE Ján Haščík, Branislav Vrban, Jakub Lüley, Štefan Čerba, Filip Osuský, Vladimír Nečas Slovak University of Technology
More informationA new neutron monitor for pulsed fields at high-energy accelerators
A new neutron monitor for pulsed fields at high-energy accelerators Marlies Luszik-Bhadra *, Eike Hohmann Physikalisch-Technische Bundesanstalt, Bundesallee 100, D-38116, Braunschweig, Germany. Abstract.
More informationMeasurement of induced radioactivity in air and water for medical accelerators
Measurement of induced radioactivity in air and water for medical accelerators K. Masumoto 1, K. Takahashi 1, H. Nakamura 1, A. Toyoda 1, K. Iijima 1, K. Kosako 2, K. Oishi 2, F. Nobuhara 1 High Energy
More informationRenewed whole-body counting chamber in STUK
Renewed whole-body counting chamber in STUK Seminar DTU Nutech, Roskilde, Denmark Tiina Torvela, Tero Karhunen, Maarit Muikku Environmental Radiation Surveillance and Emergency Preparedness Whole-body
More informationApplications of MCBEND
Serco Assurance Applications of MCBEND Presentation to NPL Workshop on Monte Carlo codes by Pat Cowan The ANSWERS Software Service Serco Assurance Overview The MCBEND Code Traditional Applications Industrial
More informationShielded Scintillator for Neutron Characterization
Shielded Scintillator for Neutron Characterization A Thesis Submitted in Partial Fulfillment of the Requirements for Graduation with Research Distinction in Engineering Physics By Patrick X. Belancourt
More informationUse of phoswich detector for simultaneous monitoring of high energy photon and its applications in in vivo lung counting
Page 1 of 8 Use of phoswich detector for simultaneous monitoring of high energy photon and its applications in in vivo lung counting Abstract Manohari M, Mathiyarasu R, Rajagopal V and Venkatraman B Radiation
More informationLower Bound of Optimization for the Public Considering Dose Distribution of Radiation due to Natural Background Radiation
Lower Bound of Optimization for the Public Considering Dose Distribution of Radiation due to Natural Background Radiation Takatoshi Hattori a* a Central Research Institute of Electric Power Industry, Radiation
More informationTECHNICAL WORKING GROUP ITWG GUIDELINE ON IN-FIELD APPLICATIONS OF HIGH- RESOLUTION GAMMA SPECTROMETRY FOR ANALYSIS OF SPECIAL NUCLEAR MATERIAL
NUCLE A R FORENSIC S INTERN ATION A L TECHNICAL WORKING GROUP ITWG GUIDELINE ON IN-FIELD APPLICATIONS OF HIGH- RESOLUTION GAMMA SPECTROMETRY FOR ANALYSIS OF SPECIAL NUCLEAR MATERIAL This document was designed
More informationTRAINING IN EXTERNAL DOSIMETRY CALCULATIONS WITH COMPUTATIONAL CODES
TRAINING IN EXTERNAL DOSIMETRY CALCULATIONS WITH COMPUTATIONAL CODES S. MORATÓ, A.BERNAL, A. QUEROL, A. ABARCA, C. GÓMEZ-ZARZUELA, R.MIRÓ, G.VERDÚ Institute for Industrial, Radiophysical and Environmental
More informationFundamentals of Radionuclide Metrology
Fundamentals of Radionuclide Metrology Brian E. Zimmerman, PhD Physical Measurement Laboratory National Institute of Standards and Technology Gaithersburg, MD USA SIM Metrology Workshop Buenos Aires, Argentina
More informationMeasurement of Shielding Effectiveness of Building Blocks against 662 KeV Photons
Journal of Physical Science, Vol. 27(2), 55 65, 2016 Measurement of Shielding Effectiveness of Building Blocks against 662 KeV Photons Oluwaseun Adedoyin 1 and Abiodun Ayodeji 2* 1 Research and Infrastructural
More informationMichael G. Stabin. Radiation Protection and Dosimetry. An Introduction to Health Physics. 4) Springer
Michael G. Stabin Radiation Protection and Dosimetry An Introduction to Health Physics 4) Springer Table of Contents Preface Acknowledgments Chapter 1. Introduction to Health Physics 1 1.1 Definition of
More informationMeasurements with the new PHE Neutron Survey Instrument
Measurements with the new PHE Neutron Survey Instrument Neutron Users Club Meeting National Physical Laboratory 16 th October 2013 Jon Eakins, Rick Tanner and Luke Hager Centre for Radiation, Chemicals
More informationCharacterization and Monte Carlo simulations for a CLYC detector
Characterization and Monte Carlo simulations for a CLYC detector A. Borella 1, E. Boogers 1, R.Rossa 1, P. Schillebeeckx 1 aborella@sckcen.be 1 SCK CEN, Belgian Nuclear Research Centre JRC-Geel, Joint
More informationInteractive Web Accessible Gamma-Spectrum Generator & EasyMonteCarlo Tools
10th Nuclear Science Training Course with NUCLEONICA, Cesme, Turkey, 8-10 October, 2008 1 Interactive Web Accessible Gamma-Spectrum Generator & EasyMonteCarlo Tools A.N. Berlizov ITU - Institute for Transuranium
More informationJournal of Radiation Protection and Research
1) SANG BUM HONG et al.: IN SITU MEASUREMENT OF DEPTH DISTRIBUTIONS Journal of Radiation Protection and Research pissn 2508-1888 eissn 2466-2461 http://dx.doi.org/10.14407/jrpr.2016.41.2.173 Paper Received
More informationNeutronics Experiments for ITER at JAERI/FNS
Neutronics Experiments for ITER at JAERI/FNS C. Konno 1), F. Maekawa 1), Y. Kasugai 1), Y. Uno 1), J. Kaneko 1), T. Nishitani 1), M. Wada 2), Y. Ikeda 1), H. Takeuchi 1) 1) Japan Atomic Energy Research
More informationQuartz-Crystal Spectrometer for the Analysis of Plutonium K X-Rays
Quartz-Crystal Spectrometer for the Analysis of Plutonium K X-Rays Alison V. Goodsell, William S. Charlton alisong@tamu.edu, charlton@ne.tamu.edu Nuclear Security Science & Policy Institute Texas A&M University,
More informationWM2016 Conference, March 6 10, 2016, Phoenix, Arizona, USA. Recovering New Type of Sources by Off-Site Source Recovery Project for WIPP Disposal-16604
Recovering New Type of Sources by Off-Site Source Recovery Project for WIPP Disposal-16604 Ioana Witkowski, Anthony Nettleton, Alex Feldman Los Alamos National Laboratory INTRODUCTION TO OSRP ACTIVITIES
More information1. What would be the dose rate of two curies of 60Co with combined energies of 2500 kev given off 100% of the time?
1.11 WORKSHEET #1 1. What would be the dose rate of two curies of 60Co with combined energies of 500 kev given off 100% of the time?. What would be the dose rate of 450 mci of 137Cs (gamma yield is 90%)?
More informationDetermination of Photon Ambient Dose Buildup Factors for Radiological Applications for Points and Plaque Source Configurations Using MCNP5
Determination of Photon Ambient Dose Buildup Factors for Radiological Applications for Points and Plaque Source Configurations Using MCNP5 P. Deatanyah 1, C.C. Arwui 1, S. Wotorchi- Gordon 1, H. Lawluvi
More informationCalculations of Photoneutrons from Varian Clinac Accelerators and Their Transmissions in Materials*
SLAC-PUB-70 Calculations of Photoneutrons from Varian Clinac Accelerators and Their Transmissions in Materials* J. C. Liu, K. R. Kase, X. S. Mao, W. R. Nelson, J. H. Kleck, and S. Johnson ) Stanford Linear
More informationDESIGN, DEVELOPMENT AND TESTING OF AN AUTOMATED SEGMENTED GAMMA SCANNER FOR MEASURING NUCLEAR POWER STATION RADIOACTIVE WASTE
15-A-473-INMM ABSTRACT DESIGN, DEVELOPMENT AND TESTING OF AN AUTOMATED SEGMENTED GAMMA SCANNER FOR MEASURING NUCLEAR POWER STATION RADIOACTIVE WASTE John A. Mason, Marc R. Looman, L. V. Odell, Adam Poundall
More informationAn Optimized Gamma-ray Densitometry Tool for Oil Products Determination
International Journal of Innovation and Applied Studies ISSN 2028-9324 Vol. 4 No. 2 Oct. 2013, pp. 408-412 2013 Innovative Space of Scientific Research Journals http://www.issr-journals.org/ijias/ An Optimized
More informationCalibration of the GNU and HSREM neutron survey instruments
Calibration of the GNU and HSREM neutron survey instruments Neutron Users Club Meeting National Physical Laboratory 20 th October 2015 J. S. Eakins 1, L. G. Hager 1, J. W. Leake 2, R. S. Mason 2 and R.
More informationCollimated LaBr 3 detector response function in radioactivity analysis of nuclear waste drums
Nuclear Science and Techniques 4 (13) 63 Collimated LaBr 3 detector response function in radioactivity analysis of nuclear waste drums QIAN Nan 1 WANG Dezhong 1,* WANG Chuan ZHU Yuelong MAUERHOFER Eric
More informationBonner Sphere Spectrometer. Cruzate, J.A.; Carelli, J.L. and Gregori, B.N.
Bonner Sphere Spectrometer Cruzate, J.A.; Carelli, J.L. and Gregori, B.N. Presentado en: Workshop on Uncertainty Assessment in Computational Dosimetry: a Comparison of Approaches. Bologna, Italia, 8-10
More informationSimulation of Personal Protective Equipment Exposure to Radioactive Particulates. A Master s Level Submission.
Simulation of Personal Protective Equipment Exposure to Radioactive Particulates M. Roeterink 1*, E.F.G. Dickson 1, P. Bodurtha 1, and E.C. Corcoran 1 1 Royal Military College of Canada, Ontario, Canada
More informationACTIVATION ANALYSIS OF DECOMISSIONING OPERATIONS FOR RESEARCH REACTORS
ACTIVATION ANALYSIS OF DECOMISSIONING OPERATIONS FOR RESEARCH REACTORS Hernán G. Meier, Martín Brizuela, Alexis R. A. Maître and Felipe Albornoz INVAP S.E. Comandante Luis Piedra Buena 4950, 8400 San Carlos
More informationUNCORRECTED PROOF. Table of Contents
00-Stabin-Prelims SNY001-Stabin (Typeset by spi publisher services, Delhi) vii of xvi June 1, 2007 17:15 Preface xiii Acknowledgments xv Chapter 1. Introduction to Health Physics 1 1.1 Definition of Health
More informationCharacterization of Large Structures & Components
Structures & Components KEY BENEFITS Key Drivers: Lack of good knowledge about the position, the identification and the radiological specification of contamination on or inside large components. Significant
More informationRadiation Protection Dosimetry (2006), Vol. 118, No. 3, pp Advance Access publication 6 October 2005
Radiation Protection Dosimetry (2006), Vol. 118, No. 3, pp. 233 237 Advance Access publication 6 October 2005 doi:10.1093/rpd/nci353 DOSE BUILD UP CORRECTION FOR RADIATION MONITORS IN HIGH-ENERGY BREMSSTRAHLUNG
More informationVERIFICATION OF MONTE CARLO CALCULATIONS OF THE NEUTRON FLUX IN THE CAROUSEL CHANNELS OF THE TRIGA MARK II REACTOR, LJUBLJANA
International Conference Nuclear Energy for New Europe 2002 Kranjska Gora, Slovenia, September 9-12, 2002 www.drustvo-js.si/gora2002 VERIFATION OF MONTE CARLO CALCULATIONS OF THE NEUTRON FLUX IN THE CAROUSEL
More informationApplied Nuclear Science Educational, Training & Simulation Systems
WWW.NATS-USA.COM Applied Nuclear Science Educational, Training & Simulation Systems North American Technical Services Bridging Technology with the Latest in Radiation Detection Systems The Center For Innovative
More informationK 40 activity and Detector Efficiency
K 40 activity and Detector Efficiency Your goal in this experiment is to determine the activity of a salt substitute purchased in a local store. The salt subsitute is pure KCl. Most of the potassium found
More informationEFFICIENCY CALIBRATION STUDIES FOR GAMMA SPECTROMETRIC SYSTEMS: THE INFLUENCE OF DIFFERENT PARAMETERS
NUCLEAR PHYSICS EFFICIENCY CALIBRATION STUDIES FOR GAMMA SPECTROMETRIC SYSTEMS: THE INFLUENCE OF DIFFERENT PARAMETERS MAGDALENA TOMA 1, OCTAVIAN SIMA 2, CARMEN CRISTACHE 1, FELICIA DRAGOLICI 1, LAURENÞIU
More informationOutline Chapter 14 Nuclear Medicine
Outline Chapter 14 uclear Medicine Radiation Dosimetry I Text: H.E Johns and J.R. Cunningham, The physics of radiology, 4 th ed. http://www.utoledo.edu/med/depts/radther Introduction Detectors for nuclear
More informationDETECTORS. I. Charged Particle Detectors
DETECTORS I. Charged Particle Detectors A. Scintillators B. Gas Detectors 1. Ionization Chambers 2. Proportional Counters 3. Avalanche detectors 4. Geiger-Muller counters 5. Spark detectors C. Solid State
More informationSECTION 8 Part I Typical Questions
SECTION 8 Part I Typical Questions 1. For a narrow beam of photons, the relaxation length is that thickness of absorber that will result in a reduction of in the initial beam intensity. 1. 1/10. 2. 1/2.
More informationGeorgia Institute of Technology. Radiation Detection & Protection (Day 3)
Georgia Institute of Technology The George W. Woodruff School of Mechanical Engineering Nuclear & Radiological Engineering/Medical Physics Program Ph.D. Qualifier Exam Spring Semester 2009 Your ID Code
More informationMonte Carlo modelling of a NaI(Tl) scintillator detectors using MCNP simulation code
Journal of Materials and Environmental Sciences ISSN : 2028-2508 Copyright 2017, University of Mohammed Premier Oujda Morocco J. Mater. Environ. Sci., 2017 Volume 8, Issue 12, Page 4560-4565 http://www.jmaterenvironsci.com
More informationThe Neutron Diagnostic Experiment for Alcator C-Mod
PFC/JA-9-16 The Neutron Diagnostic Experiment for Alcator C-Mod C. L. Fiore, R. S. Granetz Plasma Fusion Center Massachusetts Institute of Technology -Cambridge, MA 2139 May, 199 To be published in Review
More informationFast-Neutron Production via Break-Up of Deuterons and Fast-Neutron Dosimetry
Fast-Neutron Production via Break-Up of Deuterons and Fast-Neutron Dosimetry F. Gutermuth *, S. Beceiro, H. Emling, G. Fehrenbacher, E. Kozlova, T. Radon, T. Aumann, T. Le Bleis, K. Boretzky, H. Johansson,
More informationFusion/transmutation reactor studies based on the spherical torus concept
FT/P1-7, FEC 2004 Fusion/transmutation reactor studies based on the spherical torus concept K.M. Feng, J.H. Huang, B.Q. Deng, G.S. Zhang, G. Hu, Z.X. Li, X.Y. Wang, T. Yuan, Z. Chen Southwestern Institute
More informationESTIMATION OF 90 SCATTERING COEFFICIENT IN THE SHIELDING CALCULATION OF DIAGNOSTIC X-RAY EQUIPMENT
Proceedings of the Eleventh EGS4 Users' Meeting in Japan, KEK Proceedings 2003-15, p.107-113 ESTIMATION OF 90 SCATTERING COEFFICIENT IN THE SHIELDING CALCULATION OF DIAGNOSTIC X-RAY EQUIPMENT K. Noto and
More informationCurrent and Recent ICRU Activities in Radiation Protection Dosimetry and Measurements
Current and Recent ICRU Activities in Radiation Protection Dosimetry and Measurements Hans-Georg Menzel International Commission on Radiation Units and Measurements (ICRU) The principal objective of ICRU
More informationInternational Journal of Scientific & Engineering Research, Volume 5, Issue 3, March-2014 ISSN
316 Effective atomic number of composite materials by Compton scattering - nondestructive evaluation method Kiran K U a, Ravindraswami K b, Eshwarappa K M a and Somashekarappa H M c* a Government Science
More informationBasic hands-on gamma calibration for low activity environmental levels
Basic hands-on gamma calibration for low activity environmental levels Iolanda Osvath Presented by Mats Eriksson Environment Laboratories Marine Environment Laboratories, Monaco Radiometrics Laboratory
More informationWM2018 Conference, March 18-22, 2018, Phoenix, Arizona, USA. PVT and LaBr3(Ce)-based Radon Express Analyzers 18164
PVT and LaBr3(Ce)-based Radon Express Analyzers 864 Vladislav Kondrashov *, Stephen Steranka* and Glenn Paulson** * RadComm Systems Corp. 293 Portland Dr, Oakville, Ontario L6H 5S4, CANADA ** Paulson and
More informationRadionuclide Imaging MII Detection of Nuclear Emission
Radionuclide Imaging MII 3073 Detection of Nuclear Emission Nuclear radiation detectors Detectors that are commonly used in nuclear medicine: 1. Gas-filled detectors 2. Scintillation detectors 3. Semiconductor
More informationFAST NEUTRON MULTIPLICITY COUNTER
FAST NEUTRON MULTIPLICITY COUNTER Di Fulvio A. 1, Shin T. 1, Sosa C. 1, Tyler J. 1, Supic L. 1, Clarke S. 1, Pozzi S. 1, Chichester D. 2 1 Department of Nuclear Engineering and Radiological Science of
More informationGeant4 Monte Carlo code application in photon interaction parameter of composite materials and comparison with XCOM and experimental data
Indian Journal of Pure & Applied Physics Vol. 54, Februray 2016, pp. 137-143 Geant4 Monte Carlo code application in photon interaction parameter of composite materials and comparison with XCOM and experimental
More informationDesign and Use of an Interim Noble Gas Effluent Monitor at Columbia Generating Station
Design and Use of an Interim Noble Gas Effluent Monitor at Columbia Generating Station RETS-REMP & EPRI Groundwater Protection Workshop June 25-27th, 2013 Westminster, CO Eric L. Darois, CHP (RSCS) Jim
More informationDESIGN OF NEUTRON DOSE RATE METER FOR RADIATION PROTECTION IN THE EQUIVALENT DOSE
DESIGN OF NEUTRON DOSE RATE METER FOR RADIATION PROTECTION IN THE EQUIVALENT DOSE Hiroo Sato 1 and Yoichi Sakuma 2 1 International University of Health and Welfare, Kitakanemaru 2600-1, Ohtawara 324-8501
More informationMinimum Detectable Activity Estimates for a Germanium-Detector Based Spectroscopic Portal Monitor
Log 121 Minimum Detectable Activity Estimates for a Germanium-Detector Based Spectroscopic Portal Monitor Ronald M. Keyser, Frank Sergent, Timothy R. Twomey, Daniel L. Upp ORTEC 801 South Illinois Avenue
More informationU.S. EPA Superfund Counts Per Minute (CPM) Electronic Calculator Stuart A. Walker. U.S. Environmental Protection Agency, Washington, DC.
U.S. EPA Superfund Counts Per Minute (CPM) Electronic Calculator 14336 Stuart A. Walker U.S. Environmental Protection Agency, Washington, DC. 20460 ABSTRACT The U.S. Environmental Protection Agency (EPA)
More informationComparison of Several Detector Technologies for Measurement of Special Nuclear Materials i
Comparison of Several Detector Technologies for Measurement of Special Nuclear Materials i A. E. Proctor, K. R. Pohl Constellation Technology Corporation, 7887 Bryan Dairy Road, Largo Fl 33777,U.S.A. Abstract
More informationDesign, construction and characterization of a portable irradiator to calibrate installed ambient dose equivalent monitors
6 th International Congress of Metrology, 05004 (203) DOI: 0.05/ metrology/20305004 C Owned by the authors, published by EDP Sciences, 203 Design, construction and characterization of a portable irradiator
More informationCALIBRATION OF SCINTILLATION DETECTORS USING A DT GENERATOR Jarrod D. Edwards, Sara A. Pozzi, and John T. Mihalczo
CALIBRATION OF SCINTILLATION DETECTORS USING A DT GENERATOR Jarrod D. Edwards, Sara A. Pozzi, and John T. Mihalczo Oak Ridge National Laboratory Oak Ridge, TN 37831-6010 PO Box 2008 Ms6010 ABSTRACT The
More informationCharacterization of a Portable Neutron Coincidence Counter Angela Thornton and W. Charlton Texas A&M University College Station, TX
Characterization of a Portable Neutron Coincidence Counter Angela Thornton and W. Charlton Texas A&M University College Station, TX 77843 Abstract Neutron coincidence counting is a technique widely used
More informationPerformance Characterization of A New Cam System M.J. Koskelo 1, J.C. Rodgers 2, D.C. Nelson 2, A.R. McFarland 3 and C.A. Ortiz 3
Performance Characterization of A New Cam System M.J. Koskelo 1, J.C. Rodgers 2, D.C. Nelson 2, A.R. McFarland 3 and C.A. Ortiz 3 1 CANBERRA Industries, Meriden, CT 06450 2 Los Alamos National Laboratory,
More informationChapter 4 Scintillation Detectors
Med Phys 4RA3, 4RB3/6R03 Radioisotopes and Radiation Methodology 4-1 4.1. Basic principle of the scintillator Chapter 4 Scintillation Detectors Scintillator Light sensor Ionizing radiation Light (visible,
More informationRadiation Detection and Measurement
Radiation Detection and Measurement June 2008 Tom Lewellen Tkldog@u.washington.edu Types of radiation relevant to Nuclear Medicine Particle Symbol Mass (MeV/c 2 ) Charge Electron e-,! - 0.511-1 Positron
More informationISOCS / LabSOCS. Calibration software for Gamma Spectroscopy
ISOCS / LabSOCS Calibration software for Gamma Spectroscopy Counts Setup Hardware Peak Shaping Parameters Rise Time Flat Top Pole-zero Number of Channels Signal Gain Setting up a detector for measurement
More informationLarge area scintillation detector for dosimetric stand with improved light collection
NUKLEONIKA 2011;56(4):317 321 ORIGINAL PAPER Large area scintillation detector for dosimetric stand with improved light collection Bronisław Machaj, Jan Mirowicz, Ewa Kowalska Abstract. In order to improve
More informationQUALIFYING THE ZEUS SYSTEM FOR VERIFICATION OF GIC ROOM TRASH FROM RADIATION CONTROLLED AREAS AT LANL. S. C. Myers Los Alamos National Laboratory
QUALIFYING THE ZEUS SYSTEM FOR VERIFICATION OF GIC ROOM TRASH FROM RADIATION CONTROLLED AREAS AT LANL S. C. Myers Los Alamos National Laboratory ABSTRACT Los Alamos National Laboratory (LANL) radiological
More informationOutline. Absorbed Dose in Radioactive Media. Introduction. Radiation equilibrium. Charged-particle equilibrium
Absorbed Dose in Radioactive Media Chapter F.A. Attix, Introduction to Radiological Physics and Radiation Dosimetry Outline General dose calculation considerations, absorbed fraction Radioactive disintegration
More information