Spent Fuel Pool Risk Analysis for a CPR1000 Unit

Liu Weidong, Liu Leilei
{"title":"Spent Fuel Pool Risk Analysis for a CPR1000 Unit","authors":"Liu Weidong, Liu Leilei","doi":"10.1115/icone29-91949","DOIUrl":null,"url":null,"abstract":"\n After the Fukushima nuclear accident, the safety level of the spent fuel pool has gradually attracted increasing attention. This paper develops a probabilistic safety assessment (PSA) model for the spent fuel pool of a CPR1000 unit, and quantitatively evaluates the frequency of fuel damage. Possible weaknesses of the spent fuel pool are identified, and suggestions are provided to optimize the operation and management of nuclear power plants, thereby further improving the accident prevention and mitigation capabilities of the spent fuel pool and enhancing the overall safety of nuclear power plants. Through the quantitative analysis of spent fuel pool PSA, SFP fuel damage frequency of 6.99E−09/reactor year is finally developed. Compared with the core damage risk, SFP fuel damage frequency is very low, less than 1% of the core damage frequency, and the risk level is far lower than the reactor core. From the quantitative results of the initiating events, PTR discharge piping breakup and loss of offsite power are the dominant contribution to fuel damage frequency, mainly due to 1) After PTR discharge piping breaks, the ruptures can’t be isolated, and the emergency make-up is not available, finally leading to fuel damage; 2) Under refueling state, the loss of offsite power, diesel generator failure, while the main transformer, RRI/SEC, LHP/LHQ is to carry out planned maintenance, and also the emergency water supply failure jointly lead to fuel damage.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"18 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Volume 13: Risk Assessments and Management","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1115/icone29-91949","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 0

Abstract

After the Fukushima nuclear accident, the safety level of the spent fuel pool has gradually attracted increasing attention. This paper develops a probabilistic safety assessment (PSA) model for the spent fuel pool of a CPR1000 unit, and quantitatively evaluates the frequency of fuel damage. Possible weaknesses of the spent fuel pool are identified, and suggestions are provided to optimize the operation and management of nuclear power plants, thereby further improving the accident prevention and mitigation capabilities of the spent fuel pool and enhancing the overall safety of nuclear power plants. Through the quantitative analysis of spent fuel pool PSA, SFP fuel damage frequency of 6.99E−09/reactor year is finally developed. Compared with the core damage risk, SFP fuel damage frequency is very low, less than 1% of the core damage frequency, and the risk level is far lower than the reactor core. From the quantitative results of the initiating events, PTR discharge piping breakup and loss of offsite power are the dominant contribution to fuel damage frequency, mainly due to 1) After PTR discharge piping breaks, the ruptures can’t be isolated, and the emergency make-up is not available, finally leading to fuel damage; 2) Under refueling state, the loss of offsite power, diesel generator failure, while the main transformer, RRI/SEC, LHP/LHQ is to carry out planned maintenance, and also the emergency water supply failure jointly lead to fuel damage.
CPR1000机组乏燃料池风险分析
福岛核事故发生后,乏燃料池的安全水平逐渐受到越来越多的关注。建立了CPR1000机组乏燃料池的概率安全评估模型,定量评估了乏燃料池的损伤频率。找出乏燃料池可能存在的弱点,并提出优化核电站运行管理的建议,从而进一步提高乏燃料池的事故预防和缓解能力,增强核电站的整体安全性。通过对乏燃料池PSA的定量分析,最终得出了SFP燃料损坏频率为6.99E−09/堆年。与堆芯损坏风险相比,SFP燃料损坏频率非常低,不到堆芯损坏频率的1%,风险水平远低于反应堆堆芯。从启动事件的定量结果来看,PTR排放管道破裂和场外功率损失是燃料损坏频率的主要贡献,主要原因是:1)PTR排放管道破裂后,破裂无法隔离,无法进行应急修复,最终导致燃料损坏;2)在加油状态下,场外失电,柴油发电机故障,而主变压器、RRI/SEC、LHP/LHQ则进行计划检修,同时应急供水故障共同导致燃油损坏。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
求助全文
约1分钟内获得全文 求助全文
来源期刊
自引率
0.00%
发文量
0
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
确定
请完成安全验证×
copy
已复制链接
快去分享给好友吧!
我知道了
右上角分享
点击右上角分享
0
联系我们:info@booksci.cn Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术官方微信