Evaluation for self-powered neutron detector used in sodium-cooled fast reactor

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2025-06-01 Epub Date: 2025-02-16 DOI:10.1016/j.anucene.2025.111252
Sipeng Du, Qingmin Zhang, Yaodong Sang, Shiyu Liu
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Abstract

Due to the advantages of high-temperature tolerance, strong radiation resistance, tiny size, and self-powered feature, Self-Powered Neutron Detectors (SPNDs) have been widely used in the 2nd and 3rd generation reactors. The typical 4th generation reactors have higher temperature, higher neutron flux, stronger irradiation, harder neutron energy spectrum and more ununiform neutron/gamma distribution than the 3rd generation reactors. These features may affect SPND’s response performance when SPND is utilized in the 4th generation reactors. Due to its advantages in the sustainable development of nuclear fission energy, Sodium-cooled fast reactor (SFR) is chosen for this study. It is found in the study that resonant absorption plays an important role due to the harder energy spectrum in the fast reactors. In the meanwhile, current amplitude, current components, and emitter burn-up have been compared for common emitter materials, suggesting Hf is more suitable for long-term use in SFR. Finally, Hf-SPND’s response dependence on deployment position has been studied and it’s found that the current amplitude and component vary considerably with positions, indicating that position correction is required.
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评估钠冷快堆中使用的自供电中子探测器
自供电中子探测器(self-powered Neutron detector, SPNDs)由于具有耐高温、耐强辐射、体积小、自供电等优点,在第二代和第三代反应堆中得到了广泛的应用。典型的第四代反应堆比第三代反应堆具有更高的温度、更高的中子通量、更强的辐照、更硬的中子能谱和更不均匀的中子/伽马分布。当SPND用于第四代反应堆时,这些特性可能会影响SPND的响应性能。由于钠冷快堆在核裂变能可持续发展方面的优势,本文选择了钠冷快堆进行研究。研究发现,在快堆中,由于能谱较硬,共振吸收起着重要的作用。同时,对常用发射极材料的电流幅值、电流分量和发射极燃耗进行了比较,表明Hf更适合在SFR中长期使用。最后,研究了Hf-SPND响应对部署位置的依赖关系,发现当前振幅和分量随位置变化较大,需要进行位置校正。
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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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