基于成功准则分析的SGTR事故风险模型更新

IF 0.4 4区工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY

Kerntechnik Pub Date : 2022-06-24 DOI:10.1515/kern-2022-0007

M. Mohammadnia, S. M. Hoseyni, Kaveh Karimi

{"title":"基于成功准则分析的SGTR事故风险模型更新","authors":"M. Mohammadnia, S. M. Hoseyni, Kaveh Karimi","doi":"10.1515/kern-2022-0007","DOIUrl":null,"url":null,"abstract":"Abstract Success criteria analysis plays a key role in the development of realistic probabilistic safety/risk assessment (PSA/PRA) model because it provides supporting information regarding the response of complex nuclear power plant systems to different accident conditions. The current paper performs plant specific success criteria analysis for steam generator tube rupture (SGTR) accident in a typical pressurized water reactor (PWR) and demonstrates implementation of the obtained best estimate results on a risk model which has been initially developed based on expert judgment and general plant design data. The modifications on the risk model include configuration of the safety systems as well as the event tree structure. The updated PSA model shows 50% reduction in the plant core damage frequency (CDF) in comparison to the base case risk model. This highlights the importance of success criteria analysis for the development of a realistic PSA model in risk informed applications.","PeriodicalId":17787,"journal":{"name":"Kerntechnik","volume":"1 1","pages":"398 - 408"},"PeriodicalIF":0.4000,"publicationDate":"2022-06-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Updating risk model for SGTR accident based on success criteria analysis\",\"authors\":\"M. Mohammadnia, S. M. Hoseyni, Kaveh Karimi\",\"doi\":\"10.1515/kern-2022-0007\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"Abstract Success criteria analysis plays a key role in the development of realistic probabilistic safety/risk assessment (PSA/PRA) model because it provides supporting information regarding the response of complex nuclear power plant systems to different accident conditions. The current paper performs plant specific success criteria analysis for steam generator tube rupture (SGTR) accident in a typical pressurized water reactor (PWR) and demonstrates implementation of the obtained best estimate results on a risk model which has been initially developed based on expert judgment and general plant design data. The modifications on the risk model include configuration of the safety systems as well as the event tree structure. The updated PSA model shows 50% reduction in the plant core damage frequency (CDF) in comparison to the base case risk model. This highlights the importance of success criteria analysis for the development of a realistic PSA model in risk informed applications.\",\"PeriodicalId\":17787,\"journal\":{\"name\":\"Kerntechnik\",\"volume\":\"1 1\",\"pages\":\"398 - 408\"},\"PeriodicalIF\":0.4000,\"publicationDate\":\"2022-06-24\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Kerntechnik\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://doi.org/10.1515/kern-2022-0007\",\"RegionNum\":4,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q4\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Kerntechnik","FirstCategoryId":"5","ListUrlMain":"https://doi.org/10.1515/kern-2022-0007","RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}

引用次数: 0

摘要

成功准则分析为复杂核电站系统对不同事故条件的响应提供了支持信息，在现实概率安全/风险评估(PSA/PRA)模型的发展中起着关键作用。本文对典型压水堆(PWR)蒸汽发生器管破裂(SGTR)事故进行了电厂特定成功准则分析，并演示了在基于专家判断和一般电厂设计数据初步建立的风险模型上实现所获得的最佳估计结果。风险模型的修改包括安全系统的配置和事件树结构的修改。更新后的PSA模型显示，与基本情况风险模型相比，核电厂堆芯损坏频率(CDF)降低了50%。这突出了在风险知情应用中开发现实PSA模型的成功标准分析的重要性。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

查看原文本刊更多论文

Updating risk model for SGTR accident based on success criteria analysis

Abstract Success criteria analysis plays a key role in the development of realistic probabilistic safety/risk assessment (PSA/PRA) model because it provides supporting information regarding the response of complex nuclear power plant systems to different accident conditions. The current paper performs plant specific success criteria analysis for steam generator tube rupture (SGTR) accident in a typical pressurized water reactor (PWR) and demonstrates implementation of the obtained best estimate results on a risk model which has been initially developed based on expert judgment and general plant design data. The modifications on the risk model include configuration of the safety systems as well as the event tree structure. The updated PSA model shows 50% reduction in the plant core damage frequency (CDF) in comparison to the base case risk model. This highlights the importance of success criteria analysis for the development of a realistic PSA model in risk informed applications.

求助全文

通过发布文献求助，成功后即可免费获取论文全文。去求助

来源期刊

Kerntechnik 工程技术-核科学技术

CiteScore

0.90

自引率

20.00%

发文量

审稿时长

6-12 weeks

期刊介绍： Kerntechnik is an independent journal for nuclear engineering (including design, operation, safety and economics of nuclear power stations, research reactors and simulators), energy systems, radiation (ionizing radiation in industry, medicine and research) and radiological protection (biological effects of ionizing radiation, the system of protection for occupational, medical and public exposures, the assessment of doses, operational protection and safety programs, management of radioactive wastes, decommissioning and regulatory requirements).