Secondary side system design: A new calculation method for passive residual heat removal of liquid fuel molten salt reactors

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-10-18 DOI:10.1016/j.anucene.2025.111946

Shuaiyu Xue , Chong Zhou , Pinyan Huang , Yang Zou

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Abstract

The liquid molten salt reactor is distinguished by its liquid fuel, which results in the residual heat being dispersed throughout the circuit by flow. Consequently, the design calculation methods for natural circulation of the molten salt reactor diverge from traditional methods. To address the structural design calculations for this type of reactor, we propose a technique that balances the natural circulation pressure drop within the circuit with the heat transfer equilibrium of the heat exchangers between circuits. We develop the Molten-salt-reactor Passive-residual-heat-removal-system Design and Calculation Program (MPDCP) based on this approach. The results prove that the distributed residual heat within the primary circuit will reduce the heat dissipation efficiency. By using the design program, a set of passive residual heat removal systems that meet the design objectives can be obtained, effectively improving the heat dissipation efficiency by 19.1%, meeting the heat dissipation needs of the liquid fuel molten salt reactor.

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二次侧系统设计：液体燃料熔盐堆被动余热排出的一种新的计算方法

液态熔盐反应堆的特点是它的液体燃料，它导致余热通过流动分散在整个回路中。因此，熔盐堆自然循环的设计计算方法偏离了传统的计算方法。为了解决这类反应器的结构设计计算，我们提出了一种平衡回路内自然循环压降与回路间热交换器传热平衡的技术。在此基础上开发了熔盐堆被动余热排出系统设计计算程序（MPDCP）。结果表明，一次电路内分布的余热会降低散热效率。利用设计方案，获得了一套满足设计目标的被动余热排出系统，有效提高了散热效率19.1%，满足了液体燃料熔盐堆的散热需求。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

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.