{"title":"MSRE燃油箱瞬态CFD分析","authors":"Moon Hyeok Kang, Jeong Ik Lee","doi":"10.1016/j.net.2025.103659","DOIUrl":null,"url":null,"abstract":"<div><div>The Molten Salt Reactor (MSR) is one of the Generation IV reactors and it provides inherent safety and high efficiency. The Fuel Drain Tank (FDT) is a critical component in MSR for storing fuel salt in case of shutdown as well as emergency and has to be designed to remove decay heat reliably for long time. To design and predict the behavior of MSR FDT, the Oak Ridge National Lab (ORNL) assumed certain parameters in 1960s while designing the Molten Salt Reactor Experiment (MSRE). One of the key assumptions is the difference between the mixed-mean temperature of the fuel salt and the thimble tube surface temperature remains constant at 25 F. This assumption greatly simplifies the heat removal prediction as well as the design of FDT. However, the assumption was not revisited for verification in the open literature. Thus, this study attempted to verify the value using the three-dimensional transient CFD simulations which were verified through the hierarchical verification and validation methodology. Consequently, it was found that the difference between FDT mixed-mean temperature and thimble tube surface-averaged temperature was maintained around 20 K, not 25 F after thermal stratification was well-developed.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103659"},"PeriodicalIF":2.6000,"publicationDate":"2025-04-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Transient CFD analysis of MSRE fuel drain tank\",\"authors\":\"Moon Hyeok Kang, Jeong Ik Lee\",\"doi\":\"10.1016/j.net.2025.103659\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>The Molten Salt Reactor (MSR) is one of the Generation IV reactors and it provides inherent safety and high efficiency. The Fuel Drain Tank (FDT) is a critical component in MSR for storing fuel salt in case of shutdown as well as emergency and has to be designed to remove decay heat reliably for long time. To design and predict the behavior of MSR FDT, the Oak Ridge National Lab (ORNL) assumed certain parameters in 1960s while designing the Molten Salt Reactor Experiment (MSRE). One of the key assumptions is the difference between the mixed-mean temperature of the fuel salt and the thimble tube surface temperature remains constant at 25 F. This assumption greatly simplifies the heat removal prediction as well as the design of FDT. However, the assumption was not revisited for verification in the open literature. Thus, this study attempted to verify the value using the three-dimensional transient CFD simulations which were verified through the hierarchical verification and validation methodology. Consequently, it was found that the difference between FDT mixed-mean temperature and thimble tube surface-averaged temperature was maintained around 20 K, not 25 F after thermal stratification was well-developed.</div></div>\",\"PeriodicalId\":19272,\"journal\":{\"name\":\"Nuclear Engineering and Technology\",\"volume\":\"57 9\",\"pages\":\"Article 103659\"},\"PeriodicalIF\":2.6000,\"publicationDate\":\"2025-04-24\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear Engineering and Technology\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S173857332500227X\",\"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 Technology","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S173857332500227X","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}
The Molten Salt Reactor (MSR) is one of the Generation IV reactors and it provides inherent safety and high efficiency. The Fuel Drain Tank (FDT) is a critical component in MSR for storing fuel salt in case of shutdown as well as emergency and has to be designed to remove decay heat reliably for long time. To design and predict the behavior of MSR FDT, the Oak Ridge National Lab (ORNL) assumed certain parameters in 1960s while designing the Molten Salt Reactor Experiment (MSRE). One of the key assumptions is the difference between the mixed-mean temperature of the fuel salt and the thimble tube surface temperature remains constant at 25 F. This assumption greatly simplifies the heat removal prediction as well as the design of FDT. However, the assumption was not revisited for verification in the open literature. Thus, this study attempted to verify the value using the three-dimensional transient CFD simulations which were verified through the hierarchical verification and validation methodology. Consequently, it was found that the difference between FDT mixed-mean temperature and thimble tube surface-averaged temperature was maintained around 20 K, not 25 F after thermal stratification was well-developed.
期刊介绍:
Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters.
NET covers all fields for peaceful utilization of nuclear energy and radiation as follows:
1) Reactor Physics
2) Thermal Hydraulics
3) Nuclear Safety
4) Nuclear I&C
5) Nuclear Physics, Fusion, and Laser Technology
6) Nuclear Fuel Cycle and Radioactive Waste Management
7) Nuclear Fuel and Reactor Materials
8) Radiation Application
9) Radiation Protection
10) Nuclear Structural Analysis and Plant Management & Maintenance
11) Nuclear Policy, Economics, and Human Resource Development