Optimization and performance analysis of a looped separate heat pipe-based passive residual heat removal system for HTR-PM

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

Nuclear Engineering and Design Pub Date : 2025-04-18 DOI:10.1016/j.nucengdes.2025.114077

Yanzhi Li, Qi Min, Xiaowei Li, Li Zhang, Xinxin Wu, Libin Sun

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引用次数: 0

Abstract

The high-temperature gas-cooled reactor pebble-bed module (HTR-PM) is a promising advanced nuclear reactor. The passive residual heat removal system is an indispensable safety system guaranteeing the inherent safety of HTR-PM. This study presents a novel design of a looped separate heat pipe-based passive residual heat removal system for HTR-PM. The effects of the inlet air temperature, condensation length, air cooling tower height, and height difference between the evaporator and the condenser are systematically investigated. Due to the sufficient length of the evaporator, the driving force inside the looped separate heat pipe is significantly greater than the total pressure drop of the system, allowing the height difference between the condenser and the evaporator to be eliminated. The study explores the feasibility of condenser miniaturization, revealing that a 70% reduction in size is achievable. The optimal design scheme recommends reducing the condensation length of the air cooler to 70% of its original size and lowering the height of the air cooler tower to 40% of its original height. The operation in the steady state is further calculated based on the optimal design scheme. The outcome indicates that it is possible and advantageous to miniaturize the condenser to prepare and operate the separate heat pipe-based passive residual heat removal system. These findings present new opportunities for miniaturization and mobilization of the passive residual heat removal system for the high-temperature gas-cooled reactor. Further experiments should focus on implementing this strategy on small-scale separate heat pipe heat removal systems.

查看原文本刊更多论文

HTR-PM循环分离热管被动余热排除系统的优化与性能分析

高温气冷堆球床模块（HTR-PM）是一种很有发展前途的先进核反应堆。无源余热排出系统是保证高温堆堆固有安全不可缺少的安全系统。本研究提出了一种新颖的基于环形分离热管的HTR-PM被动余热排除系统设计。系统地研究了进风温度、冷凝长度、空气冷却塔高度、蒸发器与冷凝器高度差等因素对冷凝效果的影响。由于蒸发器的长度足够，环形分离热管内部的驱动力明显大于系统的总压降，从而消除了冷凝器与蒸发器之间的高度差。该研究探讨了冷凝器小型化的可行性，揭示了缩小70%的尺寸是可以实现的。优化设计方案建议将冷风机冷凝长度减小至原尺寸的70%，冷风机塔高度减小至原高度的40%。在优化设计方案的基础上，进一步对稳态运行进行了计算。结果表明，研制和运行基于分体式热管的被动余热排出系统的冷凝器小型化是可能的和有利的。这些发现为高温气冷堆被动余热排除系统的小型化和动态化提供了新的机遇。进一步的实验应侧重于在小型独立热管排热系统上实施该策略。

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.