风险指引型PSA在核电厂安全分级中的应用
详细信息 查看官网全文
- 英文论文题名：Risk-informed PSA application in nuclear power plant safety classification
- 论文作者：王金凯
- 英文论文作者：WANG Jin-kai ; China Nuclear Power Design Company ; Inc.
- 年：2015
- 作者机构：深圳中广核工程设计有限公司;
- 论文关键词：风险指引 ; 安全分级 ; 安全功能 ; 概率安全评价 ; 风险重要度
- 英文论文关键词：risk informed ; safety classification ; safety function ; probabilistic safety assessment ; risk importance
- 会议召开时间：2015-09-21
- 会议录名称：中国核科学技术进展报告（第四卷）——中国核学会2015年学术年会论文集第3册（核能动力分卷（下））
- 语种：中文
- 分类号：TM623.8
- 学会代码：EGVD
- 会议名称：中国核学会2015年学术年会
- 会议地点：中国四川绵阳
- 主办单位：中国核学会
- 学会名称：中国核学会
- 页数：8
- 文件大小：400k
- 原文格式：O
- 会议级别：全国
摘要
我国核安全法规HAF102中5.1节规定,必须对核电厂安全重要物项进行分级,且主要基于确定论方法,适当时辅以概率论方法(PSA)和工程判断。核电厂安全分级的目的是识别出安全功能并根据其安全重要性对相关的建构筑物、系统和设备(SSCs)进行识别和分类。通过合理的分级,确保每个安全级别采用合适的工程设计准则,以便使SSCs在设计、制造、建造、安装、运行、质保、维护、试验和检查等阶段中采用与其安全重要性相适应的标准要求。本文依据国际原子能机构(IAEA)的最新标准,从PSA的角度,分析总结出了一套合理可行的风险指引型安全分级方法。通过对所关注的系统部件进行风险重要度指标分析,根据相应的安全分级判断准则进行优化调整,在不影响电站安全的条件下可以提高效益,达到电厂最佳利益代价比。
In our National Nuclear Safety Regulation HAF102 Section 5.1,it requires that nuclear power plant should perform safety classification for the safety significant items.It should primarily be based on deterministic methods that are supplemented,and if necessary,using Probabilistic Safety Assessment(PSA) method and engineering judgement.The purpose of safety classification in a nuclear power plant is to identify the safety functions and to identify and classify the related Structures,Systems and Components(SSC)on the basis of their safety significance.This will ensure that appropriate engineering design rules are determined for each safety class,so that SSCs are designed,manufactured,constructed,installed,commissioned,quality assured,maintained,tested and inspected according to the standards appropriate to their safety significance.Based on the new standard of Internation Atomic Energy Agency(IAEA)of 2014,it analyzed and summaried feasible and appropriate methods for the risk informed safety classification from the point of PSA insights.By taking risk importance measures on the focused SSCs,adjusting and optimizing the SSCs classes based on the classification rules,the plant can improve the economic performance and achieve the best benefit cost ratio without impacting the safety.
In our National Nuclear Safety Regulation HAF102 Section 5.1,it requires that nuclear power plant should perform safety classification for the safety significant items.It should primarily be based on deterministic methods that are supplemented,and if necessary,using Probabilistic Safety Assessment(PSA) method and engineering judgement.The purpose of safety classification in a nuclear power plant is to identify the safety functions and to identify and classify the related Structures,Systems and Components(SSC)on the basis of their safety significance.This will ensure that appropriate engineering design rules are determined for each safety class,so that SSCs are designed,manufactured,constructed,installed,commissioned,quality assured,maintained,tested and inspected according to the standards appropriate to their safety significance.Based on the new standard of Internation Atomic Energy Agency(IAEA)of 2014,it analyzed and summaried feasible and appropriate methods for the risk informed safety classification from the point of PSA insights.By taking risk importance measures on the focused SSCs,adjusting and optimizing the SSCs classes based on the classification rules,the plant can improve the economic performance and achieve the best benefit cost ratio without impacting the safety.
引文
[1]国家核安全局.HAF201,研究堆设计安全规定,1995年6月6日。
[2]法国900MW压水堆核电站系统设计和建造规则(RCC-P 91年版+95修订)。
[3]USNRC.10CFR50.69,Risk-Informed Categorization and Treatment of Structures,Systems and Components for Nuclear Power Reactors.July 31,2002.
[4]IAEA,Safety classification of structures,systems and components in nuclear power plants,IAEA safety standards series,No.SSG-30,2014.
[5]European Utility Requirements for LWR Nuclear Power Plants,Safety Requirements,Volume 2 Chapter 1,Revision C,April,2001.
[6]Nuclear Energy Institute,10 CFR 50.69 SSC Categorization Guideline,Rev.O.July,2005.
[7]South Texas Project Nuclear Operating Company,Revised Request for Exemption to Exclude Certain Components from the Scope of Special Treatment Requirements Required by Regulations,NOC-AE-00000918,Attachment 1,August 31,2000.
[2]法国900MW压水堆核电站系统设计和建造规则(RCC-P 91年版+95修订)。
[3]USNRC.10CFR50.69,Risk-Informed Categorization and Treatment of Structures,Systems and Components for Nuclear Power Reactors.July 31,2002.
[4]IAEA,Safety classification of structures,systems and components in nuclear power plants,IAEA safety standards series,No.SSG-30,2014.
[5]European Utility Requirements for LWR Nuclear Power Plants,Safety Requirements,Volume 2 Chapter 1,Revision C,April,2001.
[6]Nuclear Energy Institute,10 CFR 50.69 SSC Categorization Guideline,Rev.O.July,2005.
[7]South Texas Project Nuclear Operating Company,Revised Request for Exemption to Exclude Certain Components from the Scope of Special Treatment Requirements Required by Regulations,NOC-AE-00000918,Attachment 1,August 31,2000.