Weixiang Wang , Kefan Zhang , Sifan Dong , Shuai Wang , Hongli Chen
{"title":"基于MOOSE框架的热管冷却堆启动特性多物理场耦合仿真分析","authors":"Weixiang Wang , Kefan Zhang , Sifan Dong , Shuai Wang , Hongli Chen","doi":"10.1016/j.nucengdes.2025.114164","DOIUrl":null,"url":null,"abstract":"<div><div>A Heat pipe reactor utilizes heat pipes to transfer fission heat from the reactor core, providing a high level of passive safety and thus representing a promising application for micro-reactors. The startup process of a heat pipe reactor is characterized by a wide range of temperature variations and a dominant expansion reactivity feedback, while also necessitating consideration of the startup issues of the frozen alkali metal heat pipes, which adds significant complexity. To analyze the characteristics of the startup process of the heat pipe reactor, this study couples the MOOSE framework with the two-dimensional high-temperature heat pipe numerical simulation code KMC-HPs, to conduct a high-precision multi-physics coupling simulation study of the nuclear-thermal–mechanical dynamics, and the accuracy and feasibility of this coupling method were validated through simulations of the ground prototype reactor KRUSTY. The analysis indicates that the heat transfer characteristics during the startup process of the heat pipes determine the temperature distribution within the reactor core. Initially, the heat transfer capability of the heat pipes is limited, resulting in a significant temperature difference. However, as the temperature rises and continuous vapor flow occurs in the evaporation section of the heat pipes, the heat transfer capability improves, leading to a more uniform temperature increase across the core with a smaller temperature difference. Mechanical analysis reveals that large thermal stresses occur at the edges of the contact surfaces between the heat pipes and the core, although these stresses remain well below the material’s yield limits. This paper elucidates the multi-physical characteristics of the heat pipe reactor startup process from a numerical simulation perspective, and the developed coupling framework provides high-precision validation for the conceptual design of heat pipe reactors.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"441 ","pages":"Article 114164"},"PeriodicalIF":1.9000,"publicationDate":"2025-05-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Analysis of heat pipe cooled reactor startup characteristics by multi-physics coupling simulation based on MOOSE framework\",\"authors\":\"Weixiang Wang , Kefan Zhang , Sifan Dong , Shuai Wang , Hongli Chen\",\"doi\":\"10.1016/j.nucengdes.2025.114164\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>A Heat pipe reactor utilizes heat pipes to transfer fission heat from the reactor core, providing a high level of passive safety and thus representing a promising application for micro-reactors. The startup process of a heat pipe reactor is characterized by a wide range of temperature variations and a dominant expansion reactivity feedback, while also necessitating consideration of the startup issues of the frozen alkali metal heat pipes, which adds significant complexity. To analyze the characteristics of the startup process of the heat pipe reactor, this study couples the MOOSE framework with the two-dimensional high-temperature heat pipe numerical simulation code KMC-HPs, to conduct a high-precision multi-physics coupling simulation study of the nuclear-thermal–mechanical dynamics, and the accuracy and feasibility of this coupling method were validated through simulations of the ground prototype reactor KRUSTY. The analysis indicates that the heat transfer characteristics during the startup process of the heat pipes determine the temperature distribution within the reactor core. Initially, the heat transfer capability of the heat pipes is limited, resulting in a significant temperature difference. However, as the temperature rises and continuous vapor flow occurs in the evaporation section of the heat pipes, the heat transfer capability improves, leading to a more uniform temperature increase across the core with a smaller temperature difference. Mechanical analysis reveals that large thermal stresses occur at the edges of the contact surfaces between the heat pipes and the core, although these stresses remain well below the material’s yield limits. This paper elucidates the multi-physical characteristics of the heat pipe reactor startup process from a numerical simulation perspective, and the developed coupling framework provides high-precision validation for the conceptual design of heat pipe reactors.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"441 \",\"pages\":\"Article 114164\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2025-05-22\",\"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/S0029549325003413\",\"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/S0029549325003413","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}
Analysis of heat pipe cooled reactor startup characteristics by multi-physics coupling simulation based on MOOSE framework
A Heat pipe reactor utilizes heat pipes to transfer fission heat from the reactor core, providing a high level of passive safety and thus representing a promising application for micro-reactors. The startup process of a heat pipe reactor is characterized by a wide range of temperature variations and a dominant expansion reactivity feedback, while also necessitating consideration of the startup issues of the frozen alkali metal heat pipes, which adds significant complexity. To analyze the characteristics of the startup process of the heat pipe reactor, this study couples the MOOSE framework with the two-dimensional high-temperature heat pipe numerical simulation code KMC-HPs, to conduct a high-precision multi-physics coupling simulation study of the nuclear-thermal–mechanical dynamics, and the accuracy and feasibility of this coupling method were validated through simulations of the ground prototype reactor KRUSTY. The analysis indicates that the heat transfer characteristics during the startup process of the heat pipes determine the temperature distribution within the reactor core. Initially, the heat transfer capability of the heat pipes is limited, resulting in a significant temperature difference. However, as the temperature rises and continuous vapor flow occurs in the evaporation section of the heat pipes, the heat transfer capability improves, leading to a more uniform temperature increase across the core with a smaller temperature difference. Mechanical analysis reveals that large thermal stresses occur at the edges of the contact surfaces between the heat pipes and the core, although these stresses remain well below the material’s yield limits. This paper elucidates the multi-physical characteristics of the heat pipe reactor startup process from a numerical simulation perspective, and the developed coupling framework provides high-precision validation for the conceptual design of heat pipe reactors.
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.