概率安全分析在福岛核事故后核电厂改进通用技术要求有效性评估中的应用
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- 英文论文题名：The application of PSA on validity assessment for general technical requirements improvement after fukushima accident
- 论文作者：曹光辉 ; 郗海英 ; 李琼哲 ; 张项飞
- 英文论文作者：CAO Guang-hui ; XI Hai-ying ; LI Qiong-zhe ; ZHANG Xiang-fei ; Suzhou Nuclear Power Research Institute Co. ; Ltd.
- 年：2015
- 作者机构：苏州热工研究院有限公司;
- 论文关键词：概率安全分析 ; 通用技术要求 ; 应急补水 ; 有效性
- 英文论文关键词：Probability Safety Analysis(PSA) ; general technology requirements ; emergency feedwater ; Validity
- 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10册（核安全分卷）
- 语种：中文
- 分类号：TM623
- 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：7
- 文件大小：285k
- 原文格式：O
- 会议级别：全国
摘要
日本福岛核事故发生以后,国家核安全局提出了8项通用技术要求(以下简称通用技术要求),要求国内核电厂在8个方面进行改进,以增强核电厂应对类福岛核事故的能力。为了验证通用技术要求对安全的贡献,本文采用概率安全分析的方法对通用技术要求的有效性进行评价,给出了概率安全评价的分析流程,并使用概率安全的分析方法评价了《应急补水及相关设备技术要求》。通过概率安全评价,配置应急补水设备为电厂事故下各种补水、供水功能提供了手段和途径,有助于保证安全。同时根据分析结果,对电厂使用移动补水设备发挥其作用预防堆芯失水事故提出了一些建议。
Following the Fukushima Nuclear Accident in Japan,National Nuclear Safety Administration(NNSA) put forward eight general technology requirements(hereinafter referred to as GTRs),which requests domestic NPPs improved from eight aspects to enhance their responding competence to nuclear accident like Fukushima's.To validate the contributions of GTRs to plant safety,this paper employs Probability Safety Analysis(PSA) to evaluate the validity of GTRs,offers the PSA analysis process,and assesses the availability of Technology Requirements on Emergency Feedzvater and Related Components.By PSA,the configured emergency feed-water can provide various water supply means and approaches to ensure the plant operation safety.Accordingly,using the analysis results,some suggestions can be proposed to the application of movable feedwater that functions on core loss of coolant accident precaution.
Following the Fukushima Nuclear Accident in Japan,National Nuclear Safety Administration(NNSA) put forward eight general technology requirements(hereinafter referred to as GTRs),which requests domestic NPPs improved from eight aspects to enhance their responding competence to nuclear accident like Fukushima's.To validate the contributions of GTRs to plant safety,this paper employs Probability Safety Analysis(PSA) to evaluate the validity of GTRs,offers the PSA analysis process,and assesses the availability of Technology Requirements on Emergency Feedzvater and Related Components.By PSA,the configured emergency feed-water can provide various water supply means and approaches to ensure the plant operation safety.Accordingly,using the analysis results,some suggestions can be proposed to the application of movable feedwater that functions on core loss of coolant accident precaution.
引文
[1]Industry-Average Performance for Components and Initiating Events at U.S.Commercial Nuclear Power Plants,NUREG/CR-6928,2007.
[2]一次侧应急补水、注入及喷淋初步设计方案[R],PK045000001DNHX03GN.
[3]二次侧临时补水及注水改进方案[R].PK450000002DNHX03GN.
[4]大亚湾核电站最终安全分析报告第9章[R].FSAR 9.1.3.5.
[5]岭澳核电站3、4号机组(功率工况)概率安全评价报告[R].2011年.
[6]岭澳核电站3、4号机组(停堆工况)概率安全评价报告[R].2011年.
[2]一次侧应急补水、注入及喷淋初步设计方案[R],PK045000001DNHX03GN.
[3]二次侧临时补水及注水改进方案[R].PK450000002DNHX03GN.
[4]大亚湾核电站最终安全分析报告第9章[R].FSAR 9.1.3.5.
[5]岭澳核电站3、4号机组(功率工况)概率安全评价报告[R].2011年.
[6]岭澳核电站3、4号机组(停堆工况)概率安全评价报告[R].2011年.