{"title":"中温热管反应堆燃料优化与瞬态分析","authors":"Zenghao Liu , Laishun Wang , Chen Hu , Binhuo Yan","doi":"10.1016/j.pnucene.2025.106049","DOIUrl":null,"url":null,"abstract":"<div><div>Micro reactors, particularly Heat Pipe cooled Reactors (HPRs), have been recognized as leading candidates for decentralized electricity markets due to their inherent safety, compact size, and transportability. However, conventional HPRs are operated at high temperatures, posing challenges related to material corrosion, thermal stresses, and startup failures. To address these issues, Medium Temperature Heat Pipe cooled Reactors (MTRs) operating at 350 °C have been proposed. In this work, three representative fuels are systematically evaluated: uranium-zirconium hydride (U-ZrH<sub>1.6</sub>), uranium dioxide (UO<sub>2</sub>), and uranium-silicide composite (U<sub>3</sub>Si<sub>2</sub>-Al). All three fuels are indicated by steady-state calculations to be suitable for normal operation of MTR. Transient simulations are conducted to assess the behavior of fuels under single and multiple heat pipe failure situations. Results are shown to indicate that while the centerline temperatures of all fuels remain below their respective melting points, the maximum temperature of U<sub>3</sub>Si<sub>2</sub>-Al fuel is found to exceed the recommended safety threshold. Although the U-ZrH<sub>1.6</sub> fuel is considered to exhibit slightly better neutron economic performance than UO<sub>2</sub>, its safety margin is determined to be significantly lower than that of UO<sub>2</sub>. In conclusion, UO<sub>2</sub> is identified as the preferred fuel candidate for MTR.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106049"},"PeriodicalIF":3.2000,"publicationDate":"2025-09-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Fuel optimization and transient analysis of a medium temperature heat pipe reactor\",\"authors\":\"Zenghao Liu , Laishun Wang , Chen Hu , Binhuo Yan\",\"doi\":\"10.1016/j.pnucene.2025.106049\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Micro reactors, particularly Heat Pipe cooled Reactors (HPRs), have been recognized as leading candidates for decentralized electricity markets due to their inherent safety, compact size, and transportability. However, conventional HPRs are operated at high temperatures, posing challenges related to material corrosion, thermal stresses, and startup failures. To address these issues, Medium Temperature Heat Pipe cooled Reactors (MTRs) operating at 350 °C have been proposed. In this work, three representative fuels are systematically evaluated: uranium-zirconium hydride (U-ZrH<sub>1.6</sub>), uranium dioxide (UO<sub>2</sub>), and uranium-silicide composite (U<sub>3</sub>Si<sub>2</sub>-Al). All three fuels are indicated by steady-state calculations to be suitable for normal operation of MTR. Transient simulations are conducted to assess the behavior of fuels under single and multiple heat pipe failure situations. Results are shown to indicate that while the centerline temperatures of all fuels remain below their respective melting points, the maximum temperature of U<sub>3</sub>Si<sub>2</sub>-Al fuel is found to exceed the recommended safety threshold. Although the U-ZrH<sub>1.6</sub> fuel is considered to exhibit slightly better neutron economic performance than UO<sub>2</sub>, its safety margin is determined to be significantly lower than that of UO<sub>2</sub>. In conclusion, UO<sub>2</sub> is identified as the preferred fuel candidate for MTR.</div></div>\",\"PeriodicalId\":20617,\"journal\":{\"name\":\"Progress in Nuclear Energy\",\"volume\":\"191 \",\"pages\":\"Article 106049\"},\"PeriodicalIF\":3.2000,\"publicationDate\":\"2025-09-18\",\"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/S0149197025004470\",\"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/S0149197025004470","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}
Fuel optimization and transient analysis of a medium temperature heat pipe reactor
Micro reactors, particularly Heat Pipe cooled Reactors (HPRs), have been recognized as leading candidates for decentralized electricity markets due to their inherent safety, compact size, and transportability. However, conventional HPRs are operated at high temperatures, posing challenges related to material corrosion, thermal stresses, and startup failures. To address these issues, Medium Temperature Heat Pipe cooled Reactors (MTRs) operating at 350 °C have been proposed. In this work, three representative fuels are systematically evaluated: uranium-zirconium hydride (U-ZrH1.6), uranium dioxide (UO2), and uranium-silicide composite (U3Si2-Al). All three fuels are indicated by steady-state calculations to be suitable for normal operation of MTR. Transient simulations are conducted to assess the behavior of fuels under single and multiple heat pipe failure situations. Results are shown to indicate that while the centerline temperatures of all fuels remain below their respective melting points, the maximum temperature of U3Si2-Al fuel is found to exceed the recommended safety threshold. Although the U-ZrH1.6 fuel is considered to exhibit slightly better neutron economic performance than UO2, its safety margin is determined to be significantly lower than that of UO2. In conclusion, UO2 is identified as the preferred fuel candidate for MTR.
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.