Improving the analysis performance of gamma spectrometer using the Monte Carlo code for accurate measurements of uranium samples

Uranium quantification and measurements represent a vital task for all used nuclear materials in nuclear technology. This work emphasizes the improvements and optimization of gamma spectrometer performance based on estimation techniques. The optimization was carried out for accurate uranium samples...

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Main Authors: K. Abd El Gawad, Zhang Zhijian, M.H. Hazzaa
Format: Article
Language:English
Published: Elsevier 2020-06-01
Series:Results in Physics
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S2211379720300358
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spelling doaj-3ba9487540744f35a9be3f05d7467b192020-11-25T03:52:40ZengElsevierResults in Physics2211-37972020-06-0117103145Improving the analysis performance of gamma spectrometer using the Monte Carlo code for accurate measurements of uranium samplesK. Abd El Gawad0Zhang Zhijian1M.H. Hazzaa2Key Discipline Laboratory of Nuclear Safety and Simulation Technology, College of Nuclear Science &Technology, Harbin Engineering University, Harbin 150001, Heilongjiang, China; Nuclear Safeguards & Physical Protection Dept., Egyptian Nuclear & Radiological Regulatory Authority (ENRRA), Cairo, Egypt; Corresponding author at: Egyptian Nuclear & Radiological Regulatory Authority (ENRRA), Cairo, Egypt.Key Discipline Laboratory of Nuclear Safety and Simulation Technology, College of Nuclear Science &Technology, Harbin Engineering University, Harbin 150001, Heilongjiang, ChinaNuclear Safeguards & Physical Protection Dept., Egyptian Nuclear & Radiological Regulatory Authority (ENRRA), Cairo, EgyptUranium quantification and measurements represent a vital task for all used nuclear materials in nuclear technology. This work emphasizes the improvements and optimization of gamma spectrometer performance based on estimation techniques. The optimization was carried out for accurate uranium samples characterization based on modeling using the Monte Carlo code (MC). The used samples are certified and nuclear materials. The measured masses were determined based on non-destructive method using a germanium detector. Using the initial MC model based on the nominal detector parameters, wide discrepancies up to 55% between measured and simulated results were obtained. Consequently, the calculated uranium masses have a high relatively variations up to 35% than the reference values. To overcome such variations, the MC model was developed through optimization of the detector dimensions. A good agreement between the results of the MC optimized model and the certified values has been obtained with a variation less than 2%.http://www.sciencedirect.com/science/article/pii/S2211379720300358Gamma spectrometryUranium samplesComputational codeOptimized detector model
collection DOAJ
language English
format Article
sources DOAJ
author K. Abd El Gawad
Zhang Zhijian
M.H. Hazzaa
spellingShingle K. Abd El Gawad
Zhang Zhijian
M.H. Hazzaa
Improving the analysis performance of gamma spectrometer using the Monte Carlo code for accurate measurements of uranium samples
Results in Physics
Gamma spectrometry
Uranium samples
Computational code
Optimized detector model
author_facet K. Abd El Gawad
Zhang Zhijian
M.H. Hazzaa
author_sort K. Abd El Gawad
title Improving the analysis performance of gamma spectrometer using the Monte Carlo code for accurate measurements of uranium samples
title_short Improving the analysis performance of gamma spectrometer using the Monte Carlo code for accurate measurements of uranium samples
title_full Improving the analysis performance of gamma spectrometer using the Monte Carlo code for accurate measurements of uranium samples
title_fullStr Improving the analysis performance of gamma spectrometer using the Monte Carlo code for accurate measurements of uranium samples
title_full_unstemmed Improving the analysis performance of gamma spectrometer using the Monte Carlo code for accurate measurements of uranium samples
title_sort improving the analysis performance of gamma spectrometer using the monte carlo code for accurate measurements of uranium samples
publisher Elsevier
series Results in Physics
issn 2211-3797
publishDate 2020-06-01
description Uranium quantification and measurements represent a vital task for all used nuclear materials in nuclear technology. This work emphasizes the improvements and optimization of gamma spectrometer performance based on estimation techniques. The optimization was carried out for accurate uranium samples characterization based on modeling using the Monte Carlo code (MC). The used samples are certified and nuclear materials. The measured masses were determined based on non-destructive method using a germanium detector. Using the initial MC model based on the nominal detector parameters, wide discrepancies up to 55% between measured and simulated results were obtained. Consequently, the calculated uranium masses have a high relatively variations up to 35% than the reference values. To overcome such variations, the MC model was developed through optimization of the detector dimensions. A good agreement between the results of the MC optimized model and the certified values has been obtained with a variation less than 2%.
topic Gamma spectrometry
Uranium samples
Computational code
Optimized detector model
url http://www.sciencedirect.com/science/article/pii/S2211379720300358
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AT mhhazzaa improvingtheanalysisperformanceofgammaspectrometerusingthemontecarlocodeforaccuratemeasurementsofuraniumsamples
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