Investigation of fast and cost-effective partial defect detector for spent fuel transfer verification to enhance nuclear safeguards

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-11-13 DOI:10.1016/j.anucene.2024.111045
Yeongjun Kim , Haneol Lee , Man-Sung Yim
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Abstract

The current nuclear safeguards approach to spent nuclear fuel inspection at nuclear power stations is based on item counting and limited partial defect analysis. With the expected surge in spent fuel storage, limited spent fuel storage pool capacity, and the increasing need for transferring fuel to long-term storage facilities, there is a growing demand for more efficient and cost-effective nuclear safeguards approaches for nuclear materials management in civilian nuclear power facilities. This study proposes a scintillator-based indirect gamma detector for spent fuel inventory screening inspection, specifically designed for use in interim storage pools prior to fuel transfer to difficult-to-access storage. This paper presents the design of the proposed detector, its application for spent fuel screening inventory inspection, and analysis using MCNP for partial defect detection. Results of analysis indicated that verifying a ∼ 13.6 % level of randomly distributed fuel defect for the Westinghouse 17x17 fuel assembly is possible using this approach. The performance evaluation also indicates that inspection of spent fuel assemblies of various vendor types against 1 SQ diversion may be possible.
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调查用于乏燃料转移核查的快速、经济高效的部分缺陷探测器,以加强核保障措施
目前核电站乏核燃料检查的核保障方法以项目计数和有限的局部缺陷分析为基础。随着乏燃料贮存量的预期激增、乏燃料贮存池容量有限以及将燃料转移到长期贮存设施的需求日益增加,民用核电设施的核材料管理对更高效、更具成本效益的核保障方法的需求日益增长。本研究提出了一种用于乏燃料库存筛选检查的闪烁体间接伽马探测器,专门设计用于燃料转移到难以进入的贮存设施之前的临时贮存池。本文介绍了拟议探测器的设计、其在乏燃料筛选库存检查中的应用,以及利用 MCNP 进行部分缺陷检测的分析。分析结果表明,使用这种方法可以验证西屋公司 17x17 燃料组件的随机分布燃料缺陷水平为 13.6%。性能评估还表明,可以对不同供应商类型的乏燃料组件进行 1 SQ 分流检查。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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