{"title":"评估在长期停电条件下为 APR1400 采用的混合舱内保留和舱外冷却策略","authors":"Saja Rababah , Aya Diab","doi":"10.1016/j.nucengdes.2024.113600","DOIUrl":null,"url":null,"abstract":"<div><p>The purpose of this study is to examine the success window of a hybrid in-vessel retention (IVR) strategy coupled with ex-vessel cooling (ERVC) under an extended Station Blackout (SBO). The high-power-density reactor, APR-1400, is selected and modelled using the computer code ASYST, to examine the thermal–hydraulic response and evaluate the efficacy of a hybrid IVR-ERVC strategy as the accident progresses. Specifically, the hybrid IVR-ERVC strategy refers to combining in-vessel injection as well as ex-vessel cooling to maintain the vessel integrity. Naturally, depressurization of the pressure vessel, which is a precursor to the in-vessel injection, is also applied. The hybrid IVR-ERVC strategy is meant to mitigate the accident and prevent a vessel breach using a set of operator actions within the framework of severe accident management guidelines (SAMG), capitalizing on the portable equipment of the Diverse and Flexible (FLEX) strategy. Three high level candidate actions (HLCAs), namely primary-side depressurization and in-vessel injection along with ex-vessel cooling via cavity flooding are systematically implemented to assess their effectiveness in maintaining the vessel’s integrity for a mission time of 72 h. By combining those high level actions, the corium can be cooled both internally as well as externally to avoid the critical heat flux bottleneck.</p></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"429 ","pages":"Article 113600"},"PeriodicalIF":1.9000,"publicationDate":"2024-09-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Evaluation of a hybrid in-vessel retention strategy with ex-vessel cooling for APR1400 under extended station blackout conditions\",\"authors\":\"Saja Rababah , Aya Diab\",\"doi\":\"10.1016/j.nucengdes.2024.113600\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><p>The purpose of this study is to examine the success window of a hybrid in-vessel retention (IVR) strategy coupled with ex-vessel cooling (ERVC) under an extended Station Blackout (SBO). The high-power-density reactor, APR-1400, is selected and modelled using the computer code ASYST, to examine the thermal–hydraulic response and evaluate the efficacy of a hybrid IVR-ERVC strategy as the accident progresses. Specifically, the hybrid IVR-ERVC strategy refers to combining in-vessel injection as well as ex-vessel cooling to maintain the vessel integrity. Naturally, depressurization of the pressure vessel, which is a precursor to the in-vessel injection, is also applied. The hybrid IVR-ERVC strategy is meant to mitigate the accident and prevent a vessel breach using a set of operator actions within the framework of severe accident management guidelines (SAMG), capitalizing on the portable equipment of the Diverse and Flexible (FLEX) strategy. Three high level candidate actions (HLCAs), namely primary-side depressurization and in-vessel injection along with ex-vessel cooling via cavity flooding are systematically implemented to assess their effectiveness in maintaining the vessel’s integrity for a mission time of 72 h. By combining those high level actions, the corium can be cooled both internally as well as externally to avoid the critical heat flux bottleneck.</p></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"429 \",\"pages\":\"Article 113600\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2024-09-21\",\"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/S0029549324007003\",\"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/S0029549324007003","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}
Evaluation of a hybrid in-vessel retention strategy with ex-vessel cooling for APR1400 under extended station blackout conditions
The purpose of this study is to examine the success window of a hybrid in-vessel retention (IVR) strategy coupled with ex-vessel cooling (ERVC) under an extended Station Blackout (SBO). The high-power-density reactor, APR-1400, is selected and modelled using the computer code ASYST, to examine the thermal–hydraulic response and evaluate the efficacy of a hybrid IVR-ERVC strategy as the accident progresses. Specifically, the hybrid IVR-ERVC strategy refers to combining in-vessel injection as well as ex-vessel cooling to maintain the vessel integrity. Naturally, depressurization of the pressure vessel, which is a precursor to the in-vessel injection, is also applied. The hybrid IVR-ERVC strategy is meant to mitigate the accident and prevent a vessel breach using a set of operator actions within the framework of severe accident management guidelines (SAMG), capitalizing on the portable equipment of the Diverse and Flexible (FLEX) strategy. Three high level candidate actions (HLCAs), namely primary-side depressurization and in-vessel injection along with ex-vessel cooling via cavity flooding are systematically implemented to assess their effectiveness in maintaining the vessel’s integrity for a mission time of 72 h. By combining those high level actions, the corium can be cooled both internally as well as externally to avoid the critical heat flux bottleneck.
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.