Design and transient analysis of a novel type passive residual heat removal system

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-09-16 DOI:10.1016/j.nucengdes.2025.114446

Yuepeng Bi , Genglei Xia , Chenyang Wang , Minjun Peng , Yifan Xu , Jiebo Wu

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引用次数: 0

Abstract

This study introduces an innovative air–water mixed cooling passive residual heat removal (AWMPRHR) system designed to overcome the challenges associated with long-term core cooling under the constraints of weight and space in marine nuclear power plants (MNPPs). By utilizing sub-zero Celsius temperatures air and water tanks as heat sinks, the RELAP5 code was used to assesses the performance differences between series and parallel configurations of air–water-cooled heat exchangers under conditions of short-term constant decay heat power and long-term cooling. The findings reveal that during constant decay heat power, the parallel configuration offers superior heat removal efficiency. However, in long-term cooling scenarios, the performance disparities between the two configurations are minimal. Comparative analysis with water-cooled and air-cooled systems shows that the AWMPRHR system not only significantly reduces the stack height by 89.84 % but also enhances the coolant subcooling following an SBO accident. Conversely, the air-cooled configuration reduces the tank volume by 72.63 % and ensures long-term core cooling. The minimum coolant subcooling at the core outlet was 36.19 K. The AWMPRHR system demonstrates a more efficient capability for long-term cooling of the core with smaller heat sink requirements.

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一种新型被动余热排出系统的设计与暂态分析

本研究介绍了一种创新的空气-水混合冷却被动余热去除（AWMPRHR）系统，旨在克服海洋核电站（MNPPs）在重量和空间限制下长期堆芯冷却的挑战。利用零下温度的空气和水箱作为散热器，采用RELAP5规范对空气水冷式换热器在短期恒衰热功率和长期冷却条件下串联和并联配置的性能差异进行了评估。结果表明，在恒衰减热功率下，并联结构具有较好的散热效率。然而，在长期冷却场景中，两种配置之间的性能差异是最小的。与水冷和风冷系统的对比分析表明，AWMPRHR系统不仅显著降低了89.84%的堆高，而且提高了SBO事故后冷却剂的过冷性。相反，风冷配置减少了72.63%的储罐体积，并确保长期的堆芯冷却。堆芯出口冷却剂过冷度最小值为36.19 K。AWMPRHR系统展示了更有效的核心长期冷却能力和更小的散热器要求。

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

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.