Performance analysis and structural optimization of NaK78-He plate-fin heat exchanger for space nuclear reactor power systems based on a Q3D numerical method

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-02-18 DOI:10.1016/j.nucengdes.2025.113917

Liang Yao , Rui-Tao Liu , Dan-Dan Su , Su-Ming Wang , Lu Wang , Hong-Na Zhang , Xiao-Bin Li , Feng-Chen Li

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引用次数: 0

Abstract

In space nuclear power systems, heat exchangers account for more than 50% of the total system weight. To minimize both weight and volume, this study selected a compact plate-fin heat exchanger (PFHE) as the NaK⁷⁸-He heat exchanger for the space nuclear power system. Computational fluid dynamics (CFD) simulations were employed to analyze the velocity distribution at the NaK⁷⁸ inlet side of a typical PFHE structure, and the channel design was optimized to enhance heat transfer and reduce pressure loss. To investigate the performance variations of the PFHE and further decrease its weight and volume, a simplified and accurate quasi-three-dimensional (Q3D) numerical calculation method was proposed. This method was combined with a genetic algorithm to optimize the PFHE’s size parameters. Results indicated that the uneven flow distribution on the NaK⁷⁸ side could reduce the heat flow by approximately 10% and increase pressure loss by over 500%. The optimized PFHE significantly improved flow uniformity, reducing the standard deviation of velocity distribution from 1.11 to 0.26. Furthermore, after optimization using the genetic algorithm, the PFHE achieved a 23.47% reduction in overall volume and a 22.38% decrease in weight. This study provides valuable insights for optimizing heat exchangers in space nuclear power systems and presents an efficient, rapid, and accurate method for performance evaluation and optimization in engineering applications.

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来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.