{"title":"二氧化碳与液态铅铋共晶的热液反应特性研究","authors":"Haonan Wang, Haicai Lyu, Weihao Xing, Xiaoyang Lun, Fang Liu, Ruixian Liang, Zhangpeng Guo, Fenglei Niu","doi":"10.1016/j.pnucene.2025.106064","DOIUrl":null,"url":null,"abstract":"<div><div>The integration of a secondary loop supercritical carbon dioxide (CO<sub>2</sub>) Brayton cycle with a primary loop liquid lead-bismuth (Pb-Bi) fast reactor offers promising advantages, including high efficiency and compactness, making it suitable for diverse power supply applications. However, the safety analysis of heat exchanger tube rupture incidents is a critical aspect of nuclear safety design. In the event of such an accident, CO<sub>2</sub> from the secondary loop is introduced into the liquid Pb-Bi pool, raising the question of whether a thermohydraulic reaction occurs between these two substances. This study aims to investigate the potential thermohydraulic reaction between CO<sub>2</sub> and liquid Pb-Bi, by developing an experimental setup for analyzing the reaction characteristics. The experimental results indicate that a chemical reaction indeed occurs between liquid Pb-Bi and CO<sub>2</sub>, resulting in the formation of lead oxide (PbO) and lead carbonate (PbCO<sub>3</sub>), both of which exhibit a loose structure. The quantity of the reaction products is influenced by the gas phase conditions. These findings are significant for predicting incidents involving heat exchanger tube wall failure and for nuclear safety analysis in liquid Pb-Bi-CO<sub>2</sub> reactors.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106064"},"PeriodicalIF":3.2000,"publicationDate":"2025-09-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Study on the thermohydraulic reaction characteristics of carbon dioxide and liquid lead-bismuth eutectic\",\"authors\":\"Haonan Wang, Haicai Lyu, Weihao Xing, Xiaoyang Lun, Fang Liu, Ruixian Liang, Zhangpeng Guo, Fenglei Niu\",\"doi\":\"10.1016/j.pnucene.2025.106064\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>The integration of a secondary loop supercritical carbon dioxide (CO<sub>2</sub>) Brayton cycle with a primary loop liquid lead-bismuth (Pb-Bi) fast reactor offers promising advantages, including high efficiency and compactness, making it suitable for diverse power supply applications. However, the safety analysis of heat exchanger tube rupture incidents is a critical aspect of nuclear safety design. In the event of such an accident, CO<sub>2</sub> from the secondary loop is introduced into the liquid Pb-Bi pool, raising the question of whether a thermohydraulic reaction occurs between these two substances. This study aims to investigate the potential thermohydraulic reaction between CO<sub>2</sub> and liquid Pb-Bi, by developing an experimental setup for analyzing the reaction characteristics. The experimental results indicate that a chemical reaction indeed occurs between liquid Pb-Bi and CO<sub>2</sub>, resulting in the formation of lead oxide (PbO) and lead carbonate (PbCO<sub>3</sub>), both of which exhibit a loose structure. The quantity of the reaction products is influenced by the gas phase conditions. These findings are significant for predicting incidents involving heat exchanger tube wall failure and for nuclear safety analysis in liquid Pb-Bi-CO<sub>2</sub> reactors.</div></div>\",\"PeriodicalId\":20617,\"journal\":{\"name\":\"Progress in Nuclear Energy\",\"volume\":\"191 \",\"pages\":\"Article 106064\"},\"PeriodicalIF\":3.2000,\"publicationDate\":\"2025-09-29\",\"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/S0149197025004627\",\"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/S0149197025004627","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}
Study on the thermohydraulic reaction characteristics of carbon dioxide and liquid lead-bismuth eutectic
The integration of a secondary loop supercritical carbon dioxide (CO2) Brayton cycle with a primary loop liquid lead-bismuth (Pb-Bi) fast reactor offers promising advantages, including high efficiency and compactness, making it suitable for diverse power supply applications. However, the safety analysis of heat exchanger tube rupture incidents is a critical aspect of nuclear safety design. In the event of such an accident, CO2 from the secondary loop is introduced into the liquid Pb-Bi pool, raising the question of whether a thermohydraulic reaction occurs between these two substances. This study aims to investigate the potential thermohydraulic reaction between CO2 and liquid Pb-Bi, by developing an experimental setup for analyzing the reaction characteristics. The experimental results indicate that a chemical reaction indeed occurs between liquid Pb-Bi and CO2, resulting in the formation of lead oxide (PbO) and lead carbonate (PbCO3), both of which exhibit a loose structure. The quantity of the reaction products is influenced by the gas phase conditions. These findings are significant for predicting incidents involving heat exchanger tube wall failure and for nuclear safety analysis in liquid Pb-Bi-CO2 reactors.
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.