{"title":"高温氟化盐试验设施(FLUSTFA)的运行经验:发现的问题和前进的道路","authors":"Sheng Zhang, Shuai Che, Adam Burak, Xiaodong Sun","doi":"10.1016/j.nucengdes.2024.113568","DOIUrl":null,"url":null,"abstract":"<div><p>Fluoride-salt-cooled High-temperature Reactors (FHRs) are promising Generation IV nuclear reactors, with a passive decay heat removal system serving as one of their key design features. A high-temperature FLUoride Salt Test FAcility (FLUSTFA) was designed and constructed to perform both integral-effect tests, such as validating the design of a scaled-down passive decay heat removal system, and separate-effect tests, including evaluating the thermal–hydraulic performance of compact heat exchangers. FLUSTFA utilizes FLiNaK (LiF-NaF-KF: 46.5–11.5–42 mol%) as the working fluid and operates up to 700 °C near the atmospheric pressure. It is comprised of a reservoir tank for melting and storing the salt, a primary molten salt loop that simulates the reactor primary coolant system, a secondary molten salt loop that represents the passive decay heat removal system, an air loop, and a chilled water loop, all of which are thermally coupled via heat exchangers. Several shakedown tests were carried out using high-temperature nitrogen and FLiNaK salt as the working fluid. A few issues were identified during initial operation of FLUSTFA at 550–600 °C, such as hydrogen fluoride generation and leakage, localized hot spots where excessive heat loss occurs, molten salt pump malfunctions, abnormal readings from ultrasonic flow meters, and blockage of salt charging and recycling lines. In addressing all these issues, paths forward have been successfully identified and implemented. The lessons learned are valuable in improving future design and construction of high-temperature molten salt systems for molten salt reactors, fusion reactors, and next-generation concentrated solar power plants.</p></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"429 ","pages":"Article 113568"},"PeriodicalIF":1.9000,"publicationDate":"2024-09-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Operation experience of a high-temperature fluoride salt test facility (FLUSTFA): Issues identified and paths forward\",\"authors\":\"Sheng Zhang, Shuai Che, Adam Burak, Xiaodong Sun\",\"doi\":\"10.1016/j.nucengdes.2024.113568\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><p>Fluoride-salt-cooled High-temperature Reactors (FHRs) are promising Generation IV nuclear reactors, with a passive decay heat removal system serving as one of their key design features. A high-temperature FLUoride Salt Test FAcility (FLUSTFA) was designed and constructed to perform both integral-effect tests, such as validating the design of a scaled-down passive decay heat removal system, and separate-effect tests, including evaluating the thermal–hydraulic performance of compact heat exchangers. FLUSTFA utilizes FLiNaK (LiF-NaF-KF: 46.5–11.5–42 mol%) as the working fluid and operates up to 700 °C near the atmospheric pressure. It is comprised of a reservoir tank for melting and storing the salt, a primary molten salt loop that simulates the reactor primary coolant system, a secondary molten salt loop that represents the passive decay heat removal system, an air loop, and a chilled water loop, all of which are thermally coupled via heat exchangers. Several shakedown tests were carried out using high-temperature nitrogen and FLiNaK salt as the working fluid. A few issues were identified during initial operation of FLUSTFA at 550–600 °C, such as hydrogen fluoride generation and leakage, localized hot spots where excessive heat loss occurs, molten salt pump malfunctions, abnormal readings from ultrasonic flow meters, and blockage of salt charging and recycling lines. In addressing all these issues, paths forward have been successfully identified and implemented. The lessons learned are valuable in improving future design and construction of high-temperature molten salt systems for molten salt reactors, fusion reactors, and next-generation concentrated solar power plants.</p></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"429 \",\"pages\":\"Article 113568\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2024-09-07\",\"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/S002954932400668X\",\"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/S002954932400668X","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}
Operation experience of a high-temperature fluoride salt test facility (FLUSTFA): Issues identified and paths forward
Fluoride-salt-cooled High-temperature Reactors (FHRs) are promising Generation IV nuclear reactors, with a passive decay heat removal system serving as one of their key design features. A high-temperature FLUoride Salt Test FAcility (FLUSTFA) was designed and constructed to perform both integral-effect tests, such as validating the design of a scaled-down passive decay heat removal system, and separate-effect tests, including evaluating the thermal–hydraulic performance of compact heat exchangers. FLUSTFA utilizes FLiNaK (LiF-NaF-KF: 46.5–11.5–42 mol%) as the working fluid and operates up to 700 °C near the atmospheric pressure. It is comprised of a reservoir tank for melting and storing the salt, a primary molten salt loop that simulates the reactor primary coolant system, a secondary molten salt loop that represents the passive decay heat removal system, an air loop, and a chilled water loop, all of which are thermally coupled via heat exchangers. Several shakedown tests were carried out using high-temperature nitrogen and FLiNaK salt as the working fluid. A few issues were identified during initial operation of FLUSTFA at 550–600 °C, such as hydrogen fluoride generation and leakage, localized hot spots where excessive heat loss occurs, molten salt pump malfunctions, abnormal readings from ultrasonic flow meters, and blockage of salt charging and recycling lines. In addressing all these issues, paths forward have been successfully identified and implemented. The lessons learned are valuable in improving future design and construction of high-temperature molten salt systems for molten salt reactors, fusion reactors, and next-generation concentrated solar power plants.
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.