用于放射性同位素生产全球频谱优化的分层靶设计方法

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Yu Xin , Qingquan Pan , Xiaojing Liu
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引用次数: 0

摘要

在高通量反应堆中对目标进行辐照,以生产反式钚同位素。靶的中子环境对跨钚同位素的生产效率至关重要。为了提高跨钚同位素的生产效率,有必要研究靶的优化设计。本研究以生产锎-252为例,分析了基于高通量同位素反应堆(HFIR)和高通量快堆(HFFR)的靶材自屏蔽效应对反钚同位素产量的影响。自屏蔽效应导致靶内的中子能谱变硬,并显著降低了核素的转化率。在进行了精细能谱分析后,我们提出了一种基于遗传算法(GA)的分层靶设计方法。为了降低计算成本,我们提出了固定源-燃烧耦合近似计算方法,避免了繁琐的燃烧计算,为优化提供了方向。利用这种方法,我们设计了一种最优的分层目标方案。与非分层靶相比,Cf-252 的生产效率提高了约 4.1 倍。这项研究为生产反式钚同位素的能谱分析和靶件设计提供了技术支持。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Layered target design method for global spectrum optimization of radioisotope production
Targets are irradiated in high-flux reactors to produce transplutonium isotopes. Neutron environment of the target is crucial for the production efficiency of transplutonium isotopes. To improve the production efficiency of transplutonium isotopes, it is necessary to research the optimization design of target. Taking the production of Californium-252 as an example, this study analyzed the impact of self-shielding effect in targets on the yield of transplutonium isotope based on the High Flux Isotope Reactor (HFIR) and High-Flux Fast Reactor (HFFR). The self-shielding effect leads to the hardening of the neutron spectrum inside the target and significantly reduces the conversion rate of nuclides. After conducting a refined energy spectrum analysis, we proposed a layered target design method based on the Genetic Algorithm (GA). To reduce computational costs, we propose a fixed source-burnup coupling approximate calculation method, which can avoid tedious burnup calculation and provide optimization direction. Using this method, we designed an optimal layered target scheme. Compared with non-layered target, the production efficiency of Cf-252 was increased by approximately 4.1 times. This study provides technical support for energy spectrum analysis and target design in producing transplutonium isotopes.
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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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