Research on steady-state behavior of natural circulation with internally heated fluids of liquid-fueled molten salt reactor

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2025-06-15 Epub Date: 2025-03-04 DOI:10.1016/j.anucene.2025.111320
Ying Cao , Weishi Wan , Chong Zhou
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Abstract

Liquid-fueled molten salt reactors (LFMSR) utilize internally heated fuel-salt compounds as the working fluid for the first time and the heat source and heat sink conditions are crucial for the natural circulation phenomena. This paper explored the steady-state behaviors of natural circulation of LFMSR and analyzed the impact of internal heat. By incorporating a heat source term into the liquid phase, the natural circulation governing differential equations were modified and solved using a self-developed Python code. Then, the homogeneously volumetric heat model of LFMSR was compared with the core central heat model of a traditional solid fuel reactor, the LFMSR exhibited a smaller steady-state natural circulation flow reducing the natural circulation thermal effect. Subsequently, an extended RELAP5/SCDAPSIM/MOD4.0 code for LFMSR was applied to verify the self-developed code, and their quantitative steady-state parameters showed a good match, which can be used for more complex system analyses in future works.
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液体燃料熔盐堆内热流体自然循环稳态行为研究
液体燃料熔盐堆(LFMSR)首次利用内部加热的燃料盐化合物作为工作流体,其热源和热沉条件对自然循环现象至关重要。本文探讨了LFMSR自然循环的稳态行为,并分析了内热的影响。通过在液相中加入热源项,对控制微分方程的自然循环进行了修改,并使用自行开发的Python代码进行了求解。然后,将LFMSR的均匀体积热模型与传统固体燃料堆堆芯中心热模型进行比较,发现LFMSR的稳态自然循环流量较小,减少了自然循环热效应。随后,利用LFMSR的RELAP5/SCDAPSIM/MOD4.0扩展代码对开发的代码进行了验证,结果表明,两者的定量稳态参数匹配良好,可用于后续工作中更复杂的系统分析。
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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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