多用途双模热管核反应堆动力系统热管失效事故分析

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Panxiao Li, Haocheng Zhang, Zhipeng Zhang, Chenglong Wang, Kailun Guo, Wenxi Tian, Suizheng Qiu
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引用次数: 0

摘要

本研究对多用途双模热管核反应堆动力系统的热管失效事故进行了综合分析,验证了其热安全特性。考虑到热管可靠性在反应堆运行中的重要性,在高达5%的热管同时失效的情况下,研究重点关注了三种主要失效模式——传热失效、冷凝失效和分离失效。利用基于OpenMC的核热耦合模拟和COMSOL的有限元分析(FEA)相结合的混合方法,对燃料组件的功率分布和全功率运行特性进行了量化。建立了一个包含热阻网络的三维热工模型来模拟热管的性能。结果表明,在参考工况下,所有核心部件,包括燃料棒(峰值温度1038.6 K)、包层(峰值温度1017.5 K)和热管壁(峰值温度979.2 K),均明显低于安全阈值。在三个最高功率热管(占总功率的6.67%)同时失效的情况下,最严重的温度增量(燃料峰值温度上升26.65%)发生在分离失效期间,但所有部件的温度都保持在规定的范围内。值得注意的是,由于残余热管保持运行完整性,最大传热能力保持在设计极限(8241.7 W)以下,因此减轻了级联故障。该研究证实了反应堆热冗余和热管布局的稳健性,即使在最坏的故障情况下也能确保安全运行。这些发现为热管冷却核反应堆(HPR)设计的进步提供了重要的见解。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Heat pipe failure accident analysis of the multipurpose dual-mode heat pipe nuclear reactor power system
This study conducts a comprehensive analysis of heat pipe failure accidents in the Multipurpose Dual-Mode Heat Pipe Nuclear Reactor power system to validate its thermal safety characteristics. Considering the importance of heat pipe reliability in reactor operations, the research focuses on three primary failure modes—heat transfer failure, condensation failure, and detachment failure—under scenarios where up to 5 % of heat pipes fail simultaneously. Utilizing a hybrid methodology integrating nuclear-thermal coupling simulations via OpenMC and finite element analysis (FEA) in COMSOL, the power distribution of fuel assemblies and full-power operational characteristics were quantified. A three-dimensional thermal–hydraulic model incorporating thermal resistance networks was developed to simulate heat pipe performance. Results demonstrate that under reference operating conditions, all core components, including fuel rods (peak temperature 1038.6 K), cladding (1017.5 K), and heat pipe walls (979.2 K), remain significantly below safety thresholds. In the event of simultaneous failure of the three highest-power heat pipes (6.67 % of total), the most severe temperature increments (up to 26.65 % rise in peak fuel temperature) occur during detachment failure, yet all components sustain temperatures within prescribed limits. Notably, cascading failures are mitigated as residual heat pipes maintain operational integrity, with maximum heat transfer capacities remaining below design limits (8241.7 W). The study confirms the robustness of the reactor’s thermal redundancy and heat pipe layout, ensuring safe operation even under worst-case failure scenarios. These findings provide critical insights for the advancement of heat pipe-cooled nuclear reactor (HPR) designs.
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来源期刊
Nuclear Engineering and Design
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.
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