Conceptual study of subcritical assembly with neutron generator for reactor physics experiments and neutron utilization

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-11-20 DOI:10.1016/j.anucene.2024.111039
Hiroshi Nakagomi, Kenichi Yoshioka, Tsukasa Sugita, Haruo Miyadera
{"title":"Conceptual study of subcritical assembly with neutron generator for reactor physics experiments and neutron utilization","authors":"Hiroshi Nakagomi,&nbsp;Kenichi Yoshioka,&nbsp;Tsukasa Sugita,&nbsp;Haruo Miyadera","doi":"10.1016/j.anucene.2024.111039","DOIUrl":null,"url":null,"abstract":"<div><div>In Japan, critical assemblies are regulated under the “Act on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactions” which provides guidelines for the construction and the operation of nuclear facilities: the core configurations of nuclear experiments are constrained accordingly. In addition, the nuclear facilities are required to comply with strict administrations if the nuclear facilities have more than the certain amount of nuclear fuels. On the other hand, subcritical assemblies are not subjected to the nuclear reactor regulation because the subcritical assemblies are not classified as nuclear reactors. We propose the subcritical assembly with a pulsed accelerator neutron source, which uses nuclear fuels below the regulation amount to ease maintenance and to widen experimental capabilities. Conceptual study of such system was carried out to calculate the deviation between reactivity difference in critical state and that in subcritical state by using the MCNP 6.2 code and the JENDL 4 library. Neutron source multiplication method and pulsed neutron source method were performed. The deviation can be estimated around 10 % by setting detectors in appropriate positions. Additionally, neutron radiography was studied as a simple application. The geometrical shapes of sample rods were seen clearly.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"212 ","pages":"Article 111039"},"PeriodicalIF":1.9000,"publicationDate":"2024-11-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454924007023","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0

Abstract

In Japan, critical assemblies are regulated under the “Act on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactions” which provides guidelines for the construction and the operation of nuclear facilities: the core configurations of nuclear experiments are constrained accordingly. In addition, the nuclear facilities are required to comply with strict administrations if the nuclear facilities have more than the certain amount of nuclear fuels. On the other hand, subcritical assemblies are not subjected to the nuclear reactor regulation because the subcritical assemblies are not classified as nuclear reactors. We propose the subcritical assembly with a pulsed accelerator neutron source, which uses nuclear fuels below the regulation amount to ease maintenance and to widen experimental capabilities. Conceptual study of such system was carried out to calculate the deviation between reactivity difference in critical state and that in subcritical state by using the MCNP 6.2 code and the JENDL 4 library. Neutron source multiplication method and pulsed neutron source method were performed. The deviation can be estimated around 10 % by setting detectors in appropriate positions. Additionally, neutron radiography was studied as a simple application. The geometrical shapes of sample rods were seen clearly.
查看原文
分享 分享
微信好友 朋友圈 QQ好友 复制链接
本刊更多论文
带中子发生器的次临界组件概念研究,用于反应堆物理实验和中子利用
在日本,临界组件受 "核源材料、核燃料材料和反应监管法 "的监管,该法为核设施的建造和运行提供了指导方针:核实验的核心配置受到相应的限制。此外,如果核设施拥有超过一定数量的核燃料,则必须遵守严格的管理规定。另一方面,亚临界组件不受核反应堆管理条例的约束,因为亚临界组件不属于核反应堆。我们建议亚临界组件配备脉冲加速器中子源,使用低于规定数量的核燃料,以方便维护并扩大实验能力。对这种系统进行了概念研究,利用 MCNP 6.2 代码和 JENDL 4 库计算了临界状态和亚临界状态下反应性差异的偏差。采用了中子源倍增法和脉冲中子源法。通过将探测器设置在适当的位置,可以估算出 10 % 左右的偏差。此外,还研究了中子射线照相这一简单应用。样品棒的几何形状清晰可见。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
求助全文
约1分钟内获得全文 去求助
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.
期刊最新文献
Evaluation of uranium-233 neutron capture cross section in keV region Application of data partitioned Kriging algorithm with GPU acceleration in real-time and refined reconstruction of three-dimensional radiation fields Boiling critical characteristics in narrow rectangular channel under local heat flux concentration conditions Investigation on thermal response of high temperature heat pipe under thermal mismatch conditions Numerical simulation of impurity particles migration and deposition within the 5 × 5 fuel assembly under nucleate boiling conditions
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
现在去查看 取消
×
提示
确定
0
微信
客服QQ
Book学术公众号 扫码关注我们
反馈
×
意见反馈
请填写您的意见或建议
请填写您的手机或邮箱
已复制链接
已复制链接
快去分享给好友吧!
我知道了
×
扫码分享
扫码分享
Book学术官方微信
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术
文献互助 智能选刊 最新文献 互助须知 联系我们:info@booksci.cn
Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。
Copyright © 2023 Book学术 All rights reserved.
ghs 京公网安备 11010802042870号 京ICP备2023020795号-1