Comparative analysis of nondestructive ASSAY techniques for 235U and 239Pu in structural materials at a high gamma background level

Potential techniques to identify small quantities of fissionable materials (FM) (0.001% wt.) in conditions of a high gamma background level have been reviewed and compared, and the optimal possibility for the nuclear material (NM) control in spent fuel assemblies (SFA) has been selected. It was foun...

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Main Authors: M.Yu. Kalenova, A.V. Ananyev, P.B. Baskov, S.V. Sklyarov, I.V. Kuznetsov
Format: Article
Language:English
Published: National Research Nuclear University (MEPhI) 2017-09-01
Series:Nuclear Energy and Technology
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S2452303817300699
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author M.Yu. Kalenova
A.V. Ananyev
P.B. Baskov
S.V. Sklyarov
I.V. Kuznetsov
author_facet M.Yu. Kalenova
A.V. Ananyev
P.B. Baskov
S.V. Sklyarov
I.V. Kuznetsov
author_sort M.Yu. Kalenova
collection DOAJ
description Potential techniques to identify small quantities of fissionable materials (FM) (0.001% wt.) in conditions of a high gamma background level have been reviewed and compared, and the optimal possibility for the nuclear material (NM) control in spent fuel assemblies (SFA) has been selected. It was found through numerical simulation that a system based on a passive neutron control method could be used to detect FMs indirectly when the spent nuclear fuel (SNF) burn-up and cooling time are known. Two types of detectors have been compared: 3He counters and 235U-based fission chambers. Better application prospects of 3He counters, based on the SNM-18 neutron counter, have been shown and drawbacks of passive control technique have been pointed out. An active neutron control has been found to be the best way to address the problem considered. The system's computational model shows that the signal exceeds the triple background error (both for ambient and intrinsic background from Cm isotopes) more than twelvefold. To improve the signal recording efficiency, the system has been modified to allow for irregularities in the geometrical position of structural materials (SM) in the measuring chamber. The proposed procedure makes it possible to determine in a short time the content of 239Pu, 242Cm, and 244Cm in an SFA. After the quantity of 239Pu is determined, it is possible to estimate the content of other isotopes (Am, U, Np) due to the constancy of the 239Pu mass ratio to the mass of the actinide identified.
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spelling doaj.art-84f9e7c2682244e4aa6168f62c2d46e32022-12-22T01:29:19ZengNational Research Nuclear University (MEPhI)Nuclear Energy and Technology2452-30382017-09-013319920510.1016/j.nucet.2017.08.002Comparative analysis of nondestructive ASSAY techniques for 235U and 239Pu in structural materials at a high gamma background levelM.Yu. KalenovaA.V. AnanyevP.B. BaskovS.V. SklyarovI.V. KuznetsovPotential techniques to identify small quantities of fissionable materials (FM) (0.001% wt.) in conditions of a high gamma background level have been reviewed and compared, and the optimal possibility for the nuclear material (NM) control in spent fuel assemblies (SFA) has been selected. It was found through numerical simulation that a system based on a passive neutron control method could be used to detect FMs indirectly when the spent nuclear fuel (SNF) burn-up and cooling time are known. Two types of detectors have been compared: 3He counters and 235U-based fission chambers. Better application prospects of 3He counters, based on the SNM-18 neutron counter, have been shown and drawbacks of passive control technique have been pointed out. An active neutron control has been found to be the best way to address the problem considered. The system's computational model shows that the signal exceeds the triple background error (both for ambient and intrinsic background from Cm isotopes) more than twelvefold. To improve the signal recording efficiency, the system has been modified to allow for irregularities in the geometrical position of structural materials (SM) in the measuring chamber. The proposed procedure makes it possible to determine in a short time the content of 239Pu, 242Cm, and 244Cm in an SFA. After the quantity of 239Pu is determined, it is possible to estimate the content of other isotopes (Am, U, Np) due to the constancy of the 239Pu mass ratio to the mass of the actinide identified.http://www.sciencedirect.com/science/article/pii/S2452303817300699Fissionable materialsActive assaySFAStructural material3He counterGamma background
spellingShingle M.Yu. Kalenova
A.V. Ananyev
P.B. Baskov
S.V. Sklyarov
I.V. Kuznetsov
Comparative analysis of nondestructive ASSAY techniques for 235U and 239Pu in structural materials at a high gamma background level
Nuclear Energy and Technology
Fissionable materials
Active assay
SFA
Structural material
3He counter
Gamma background
title Comparative analysis of nondestructive ASSAY techniques for 235U and 239Pu in structural materials at a high gamma background level
title_full Comparative analysis of nondestructive ASSAY techniques for 235U and 239Pu in structural materials at a high gamma background level
title_fullStr Comparative analysis of nondestructive ASSAY techniques for 235U and 239Pu in structural materials at a high gamma background level
title_full_unstemmed Comparative analysis of nondestructive ASSAY techniques for 235U and 239Pu in structural materials at a high gamma background level
title_short Comparative analysis of nondestructive ASSAY techniques for 235U and 239Pu in structural materials at a high gamma background level
title_sort comparative analysis of nondestructive assay techniques for 235u and 239pu in structural materials at a high gamma background level
topic Fissionable materials
Active assay
SFA
Structural material
3He counter
Gamma background
url http://www.sciencedirect.com/science/article/pii/S2452303817300699
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