{"title":"多用途双模热管核反应堆动力系统热管失效事故分析","authors":"Panxiao Li, Haocheng Zhang, Zhipeng Zhang, Chenglong Wang, Kailun Guo, Wenxi Tian, Suizheng Qiu","doi":"10.1016/j.nucengdes.2025.114471","DOIUrl":null,"url":null,"abstract":"<div><div>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.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"445 ","pages":"Article 114471"},"PeriodicalIF":2.1000,"publicationDate":"2025-09-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Heat pipe failure accident analysis of the multipurpose dual-mode heat pipe nuclear reactor power system\",\"authors\":\"Panxiao Li, Haocheng Zhang, Zhipeng Zhang, Chenglong Wang, Kailun Guo, Wenxi Tian, Suizheng Qiu\",\"doi\":\"10.1016/j.nucengdes.2025.114471\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>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.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"445 \",\"pages\":\"Article 114471\"},\"PeriodicalIF\":2.1000,\"publicationDate\":\"2025-09-27\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S002954932500648X\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S002954932500648X","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
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.
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.