Juin-Fu Chai, Fan-Ru Lin, Wei-Hung Hsu, Yi-Jun Kao
{"title":"核电站乏燃料池储水地震晃动试验研究","authors":"Juin-Fu Chai, Fan-Ru Lin, Wei-Hung Hsu, Yi-Jun Kao","doi":"10.1016/j.nucengdes.2025.114531","DOIUrl":null,"url":null,"abstract":"<div><div>Due to the event of Fukushima Daiichi Nuclear Power Plant in 2011, the U.S. Nuclear Regulatory Commission (NRC) requested all U.S. nuclear power plants to conduct seismic hazard re-evaluation per the newest guidance and requirements. Among them, the spent fuel pool (SFP) is considered an important facility. The related evaluation guidance provided in the Electric Power Research Institute EPRI-1025287 report emphasizes failure modes of the SFP that could result in “rapid drain-down”. One of the possible causes is the volume of water splashed out of the pool due to seismic sloshing. In EPRI-1025287 report, a very convenient yet conservative approach for estimating water splash volume was provided. To obtain more accurate results, this study employed a shaking table test of liquid storage tanks to develop a more realistic water splash volume estimation method, based on the relationship between seismic-induced sloshing height and the associated total volume of water splashed out of the tanks. In the development of this method, the use of a single-degree-of-freedom (SDOF) systems to estimate the sloshing time history is also proposed for subsequent splashed volume calculation. Furthermore, the sloshing frequency, which is related to the sloshing height and the splashed water volume, is also a key focus of the study.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"445 ","pages":"Article 114531"},"PeriodicalIF":2.1000,"publicationDate":"2025-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Experimental study on seismic sloshing of storage water for spent fuel pool in NPPs\",\"authors\":\"Juin-Fu Chai, Fan-Ru Lin, Wei-Hung Hsu, Yi-Jun Kao\",\"doi\":\"10.1016/j.nucengdes.2025.114531\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Due to the event of Fukushima Daiichi Nuclear Power Plant in 2011, the U.S. Nuclear Regulatory Commission (NRC) requested all U.S. nuclear power plants to conduct seismic hazard re-evaluation per the newest guidance and requirements. Among them, the spent fuel pool (SFP) is considered an important facility. The related evaluation guidance provided in the Electric Power Research Institute EPRI-1025287 report emphasizes failure modes of the SFP that could result in “rapid drain-down”. One of the possible causes is the volume of water splashed out of the pool due to seismic sloshing. In EPRI-1025287 report, a very convenient yet conservative approach for estimating water splash volume was provided. To obtain more accurate results, this study employed a shaking table test of liquid storage tanks to develop a more realistic water splash volume estimation method, based on the relationship between seismic-induced sloshing height and the associated total volume of water splashed out of the tanks. In the development of this method, the use of a single-degree-of-freedom (SDOF) systems to estimate the sloshing time history is also proposed for subsequent splashed volume calculation. Furthermore, the sloshing frequency, which is related to the sloshing height and the splashed water volume, is also a key focus of the study.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"445 \",\"pages\":\"Article 114531\"},\"PeriodicalIF\":2.1000,\"publicationDate\":\"2025-10-11\",\"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/S0029549325007083\",\"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/S0029549325007083","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}
Experimental study on seismic sloshing of storage water for spent fuel pool in NPPs
Due to the event of Fukushima Daiichi Nuclear Power Plant in 2011, the U.S. Nuclear Regulatory Commission (NRC) requested all U.S. nuclear power plants to conduct seismic hazard re-evaluation per the newest guidance and requirements. Among them, the spent fuel pool (SFP) is considered an important facility. The related evaluation guidance provided in the Electric Power Research Institute EPRI-1025287 report emphasizes failure modes of the SFP that could result in “rapid drain-down”. One of the possible causes is the volume of water splashed out of the pool due to seismic sloshing. In EPRI-1025287 report, a very convenient yet conservative approach for estimating water splash volume was provided. To obtain more accurate results, this study employed a shaking table test of liquid storage tanks to develop a more realistic water splash volume estimation method, based on the relationship between seismic-induced sloshing height and the associated total volume of water splashed out of the tanks. In the development of this method, the use of a single-degree-of-freedom (SDOF) systems to estimate the sloshing time history is also proposed for subsequent splashed volume calculation. Furthermore, the sloshing frequency, which is related to the sloshing height and the splashed water volume, is also a key focus of the study.
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.