{"title":"热管冷却堆高温热管束失效情形的数值研究","authors":"Jinyuan Wang, Panxiao Li, Chenglong Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu","doi":"10.1016/j.pnucene.2025.106033","DOIUrl":null,"url":null,"abstract":"<div><div>The heat pipe reactor is an innovative nuclear reactor technology that employs alkali-metal heat pipes to transfer heat efficiently. However, during operation, heat pipes face significant thermo-mechanical loads, which can lead to failures and reduced cooling performance. While numerous studies have conducted numerical simulations to investigate potential failure scenarios and assess the safety of heat pipe reactors, there remains a lack of validation against experimental data. This study evaluates the feasibility of using the thermal resistance network method for simulating accident scenarios based on experimental data from high-temperature heat pipe bundle failure tests. Results show that individual performance differences among heat pipes must be included in simulations; neglecting this can underestimate the maximum matrix temperature. Additionally, modeling failed heat pipes should not assume adiabatic boundary conditions but rather increase thermal resistance appropriately to preserve partial heat transfer capability. Using adiabatic conditions results in a higher maximum matrix temperature compared to applying increased thermal resistance. When the performance differences among individual heat pipes and the corresponding thermal resistance variations of failed heat pipes are taken into account, this approach yields a more accurate representation of the temperature distribution.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106033"},"PeriodicalIF":3.2000,"publicationDate":"2025-09-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Numerical investigation of high-temperature heat pipe bundle failure scenario for heat pipe cooled reactor\",\"authors\":\"Jinyuan Wang, Panxiao Li, Chenglong Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu\",\"doi\":\"10.1016/j.pnucene.2025.106033\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>The heat pipe reactor is an innovative nuclear reactor technology that employs alkali-metal heat pipes to transfer heat efficiently. However, during operation, heat pipes face significant thermo-mechanical loads, which can lead to failures and reduced cooling performance. While numerous studies have conducted numerical simulations to investigate potential failure scenarios and assess the safety of heat pipe reactors, there remains a lack of validation against experimental data. This study evaluates the feasibility of using the thermal resistance network method for simulating accident scenarios based on experimental data from high-temperature heat pipe bundle failure tests. Results show that individual performance differences among heat pipes must be included in simulations; neglecting this can underestimate the maximum matrix temperature. Additionally, modeling failed heat pipes should not assume adiabatic boundary conditions but rather increase thermal resistance appropriately to preserve partial heat transfer capability. Using adiabatic conditions results in a higher maximum matrix temperature compared to applying increased thermal resistance. When the performance differences among individual heat pipes and the corresponding thermal resistance variations of failed heat pipes are taken into account, this approach yields a more accurate representation of the temperature distribution.</div></div>\",\"PeriodicalId\":20617,\"journal\":{\"name\":\"Progress in Nuclear Energy\",\"volume\":\"191 \",\"pages\":\"Article 106033\"},\"PeriodicalIF\":3.2000,\"publicationDate\":\"2025-09-10\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Progress in Nuclear Energy\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0149197025004317\",\"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":"Progress in Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0149197025004317","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}
Numerical investigation of high-temperature heat pipe bundle failure scenario for heat pipe cooled reactor
The heat pipe reactor is an innovative nuclear reactor technology that employs alkali-metal heat pipes to transfer heat efficiently. However, during operation, heat pipes face significant thermo-mechanical loads, which can lead to failures and reduced cooling performance. While numerous studies have conducted numerical simulations to investigate potential failure scenarios and assess the safety of heat pipe reactors, there remains a lack of validation against experimental data. This study evaluates the feasibility of using the thermal resistance network method for simulating accident scenarios based on experimental data from high-temperature heat pipe bundle failure tests. Results show that individual performance differences among heat pipes must be included in simulations; neglecting this can underestimate the maximum matrix temperature. Additionally, modeling failed heat pipes should not assume adiabatic boundary conditions but rather increase thermal resistance appropriately to preserve partial heat transfer capability. Using adiabatic conditions results in a higher maximum matrix temperature compared to applying increased thermal resistance. When the performance differences among individual heat pipes and the corresponding thermal resistance variations of failed heat pipes are taken into account, this approach yields a more accurate representation of the temperature distribution.
期刊介绍:
Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field.
Please note the following:
1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy.
2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc.
3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.