An intercomparison of Monte Carlo codes used in gamma-ray spectrometry

Vidmar, T.; Aubineau-Lanièce, I.; Anagnostakis, M.J.; Arnold, D.; Brettner-Messler, R.; Budjáš, D.; Capogni, M.; Dias, Mauro S.; Geer, L.-E. De; Fazio, A.; Gasparro, Joël; Hult, Mikael; Hurtado, Santiago; Vargas, M. Jurado; Laubenstein, M.; Lee, K. B.; Lee, Y. K.; Lépy, Marie‐Christine; Maringer, Franz Josef; Peyrés, V.; Mille, Marie-Laure; Moralles, M.; Nour, S.; Plenteda, Romano; Montero, M.P. Rubio; Sima, O.; Tomei, C.; Vidmar, Gaj

doi:10.1016/j.apradiso.2008.02.015

Cited by 67 publications

(21 citation statements)

References 3 publications

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“…Undoubtedly, an improper value will be considered for the detector radius, and this will strongly affect the values of the efficiencies calculated by simulation or evaluation by analytical computation, while the transfer factor is slightly sensitive to this incorrect value, because a wrong value will simultaneously affect both the efficiency calculated for the reference geometry and that for the geometry of interest and their ratio will be practically unchanged. The sensitivity of the efficiency to details of the input data and to the computation model was clearly revealed by Vidmar in 2008 [16]. Clearly, the efficiency transfer method offers better results in the case when the measurements of interest are similar to the reference measurements.…”

Section: The Efficiency Transfermentioning

confidence: 97%

Dedicated Monte Carlo Procedures Applied in Gamma-ray Spectrometry Used in Decommissioning of Nuclear Facilities

Gurau¹

2016

Nuclear Material Performance

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Because the experimental efficiency calibration is limited to several measurement geometries and cannot be applied directly to all measurement configurations, the efficiency transfer method for the efficiency computation was applied using ETNA software. An approach using efficiencies measured with point sources combined with theoretical procedures was applied for obtaining the peak efficiency ε(E) for disk sources measured with a NaI(Tl) detector. The transfer method was applied for the computation of the efficiency of an HPGe detector using as a reference a point source placed at 10 cm height from the face of the detector. The method was applied both for point sources and volume sources with varied compositions and densities. To correct the experimental values of the efficiencies, coincidence summing effects were evaluated using GESPECOR Monte Carlo code. The study of the response function characterization of the ISOCART and Segmented Gamma Scanner WS1100 gamma-ray spectrometry systems was related. GEANT 3.21 Monte Carlo code was used to simulate the spectra expected to be obtained for the photon energy range from 50 to 2000 keV. A big volume represented by a 220l cylindrical source was considered to be measured with the two systems. The full energy peak efficiency and the total efficiency were evaluated.

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Section: The Efficiency Transfermentioning

confidence: 97%

Dedicated Monte Carlo Procedures Applied in Gamma-ray Spectrometry Used in Decommissioning of Nuclear Facilities

Gurau¹

2016

Nuclear Material Performance

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“…Gamma-ray spectrometers are systems that have wide uses in various experimental applications. These detectors are utilized for the assay purposes of radionuclides that emit gamma rays and in measuring radioactivity at nuclear facilities (El-Gammal, El-Nagdy, Rizk, Shawky, & Samei, 2005;Vidmar et al, 2008). Amongst gamma-ray detectors is a HPGe detector that has many applications in the radioactive and nuclear field.…”

Section: Gamma Calculationsmentioning

confidence: 99%

Countering distortion scenarios outcome from shaping and the chemical mixing in U3O8-Al compact using reliable model

Shaban

Hazzaa

El-Tayebany

et al. 2020

Journal of Radiation Research and Applied Sciences

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Overcoming the distortion appears in the production of fuel plate in Material Testing Reactor type (MTR) type fuel is considered an important challenge in safeguard measurements. A methodology is presented using a mathematical model and MCNP code to minimize defects that result from the chemical mixing in U 3 O 8-Al Compact. The mathematical model relates between distance (sampledetector) and the count rate of 185.7 keV gamma energy line that characterize U-235 isotope. The tested samples are compact of uranium oxide and aluminum alloy. The mixing ratio is 48 volume % of U 3 O 8 , and 52 volume % of Al-metal powder. The sample volume is 35.48 cm 3 and its density is 4.8 g/cm 3. The manufacturer data concerning U-235 mass is 0.7785 and 21.3 g. The compact has a parallelpiped shape that has dimensions of 69, 8.5 and 60.5 mm. The used instrument is a High-Purity Germanium detector (HPGe) and the distances between the detector-sample are in the range from 9.5 to 11 cm. Results coming from the model and MCNP-5 complement each other and validated by comparing with declared values. The method could play an important role in safeguards and processes of Quality Control (QC) in the Fuel Manufacturing Pilot Plant (FMPP).

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“…High Pu rity Ger ma nium de tec tor (HPGe) [Canberra; model GL0515R with an ac tive area of 540 mm 2 , 1.5 cm height, and 122 keV FWHM at 540 eV] was used in the MCNP in puts. Multi-chan nel an a lyzer [inspec tor, Model IN2K], to col lect the in put en ergy pulses, the de tec tor was ad justed at high volt age (2500V) [10][11][12][13]. A set of tested NM sam ples were used for ex e cut ing the com pu ta tional cal cu la tions.…”

Section: Gamma Cal Cu La Tionsmentioning

confidence: 99%

A new methodology for determination of water of crystallization for uranyl nitrate samples using scanning electron microscope, energy dispersive X-ray, and MCPN-5

2019

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An intercomparison of Monte Carlo codes used in gamma-ray spectrometry

Cited by 67 publications

References 3 publications

Dedicated Monte Carlo Procedures Applied in Gamma-ray Spectrometry Used in Decommissioning of Nuclear Facilities

Dedicated Monte Carlo Procedures Applied in Gamma-ray Spectrometry Used in Decommissioning of Nuclear Facilities

Countering distortion scenarios outcome from shaping and the chemical mixing in U3O8-Al compact using reliable model

A new methodology for determination of water of crystallization for uranyl nitrate samples using scanning electron microscope, energy dispersive X-ray, and MCPN-5

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