Development of neutron spectrum analysis method to assess the content of fissile isotopes in SFA

The paper presents the integrated neutron spectrum analysis as a potential method for estimating the contents of fissile isotopes in SFAs. Two method implementation variants are described: (1) measurement of SFA average transmission and (2) measurement of sample average transmission in the spectrum...

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Main Author: A.V. Mitskevich
Format: Article
Language:English
Published: National Research Nuclear University (MEPhI) 2015-11-01
Series:Nuclear Energy and Technology
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S2452303816000169
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author A.V. Mitskevich
author_facet A.V. Mitskevich
author_sort A.V. Mitskevich
collection DOAJ
description The paper presents the integrated neutron spectrum analysis as a potential method for estimating the contents of fissile isotopes in SFAs. Two method implementation variants are described: (1) measurement of SFA average transmission and (2) measurement of sample average transmission in the spectrum that has passed a SFA. The authors describe the dependences of SFA average transmission on its content of the required isotope obtained by means of two types of detectors: helium counter tube and fission chamber. Also, the authors propose a method to estimate SFA burn-up by means of the integrated NSA. In addition, SFA residence time influence on transmission is estimated.
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spelling doaj.art-6738881c33bb45a2acd12f6875a11a3b2022-12-21T23:30:35ZengNational Research Nuclear University (MEPhI)Nuclear Energy and Technology2452-30382015-11-011320220710.1016/j.nucet.2016.02.001Development of neutron spectrum analysis method to assess the content of fissile isotopes in SFAA.V. MitskevichThe paper presents the integrated neutron spectrum analysis as a potential method for estimating the contents of fissile isotopes in SFAs. Two method implementation variants are described: (1) measurement of SFA average transmission and (2) measurement of sample average transmission in the spectrum that has passed a SFA. The authors describe the dependences of SFA average transmission on its content of the required isotope obtained by means of two types of detectors: helium counter tube and fission chamber. Also, the authors propose a method to estimate SFA burn-up by means of the integrated NSA. In addition, SFA residence time influence on transmission is estimated.http://www.sciencedirect.com/science/article/pii/S2452303816000169Spent fuelNeutron spectrum analysis235U and 239Pu content assessmentHelium counter tubeFission chambertransmissionFuel assemblyResidence time
spellingShingle A.V. Mitskevich
Development of neutron spectrum analysis method to assess the content of fissile isotopes in SFA
Nuclear Energy and Technology
Spent fuel
Neutron spectrum analysis
235U and 239Pu content assessment
Helium counter tube
Fission chamber
transmission
Fuel assembly
Residence time
title Development of neutron spectrum analysis method to assess the content of fissile isotopes in SFA
title_full Development of neutron spectrum analysis method to assess the content of fissile isotopes in SFA
title_fullStr Development of neutron spectrum analysis method to assess the content of fissile isotopes in SFA
title_full_unstemmed Development of neutron spectrum analysis method to assess the content of fissile isotopes in SFA
title_short Development of neutron spectrum analysis method to assess the content of fissile isotopes in SFA
title_sort development of neutron spectrum analysis method to assess the content of fissile isotopes in sfa
topic Spent fuel
Neutron spectrum analysis
235U and 239Pu content assessment
Helium counter tube
Fission chamber
transmission
Fuel assembly
Residence time
url http://www.sciencedirect.com/science/article/pii/S2452303816000169
work_keys_str_mv AT avmitskevich developmentofneutronspectrumanalysismethodtoassessthecontentoffissileisotopesinsfa