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

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
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引用次数: 0

摘要

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