期刊文献+

高温气冷堆压力容器侧向支承地震易损性的敏感性分析 被引量:2

Sensitivity Analysis for Seismic Fragilities of Lateral Supports of RPV for High Temperature Gas-Cooled Reactor
原文传递
导出
摘要 反应堆压力容器(RPV)侧向支承是高温气冷堆地震风险的关键贡献物项,对于反应堆地震安全至关重要。本文确定了高温气冷堆RPV侧向支承的地震易损性变量,分析出易损性变量因子的合理取值,计算得到侧向支承的地震易损性曲线和高置信度低失效概率(HCLPF)抗震能力,挑选出易损性变量中的关键参数,并研究了RPV侧向支承HCLPF抗震能力对易损性关键参数的敏感性。结果表明,侧向支承的抗震能力明显高于设计基准地震动,易损性对于关键参数变异并不敏感。 The lateral supports of reactor pressure vessel (RPV)are expected as a major contributor to the seismic risk of high temperature gas-cooled reactor (HTR)and are crucial to the safety of HTR RPV under seismic events.In this paper,we focus on the identification of seismic fragility variables,the analysis of reasonable factor values of fragility variables,the calculation of High Confidence Low Probabilistic Failure (HCLPF)Capacity and seismic fragility Curves,the selection of the key parameters among fragility variables,and the exploration into the sensitivity of HCLPF to these key parameters of seismic fragility analysis.The results show that the HCLPF of lateral supports is much higher than the design basis earthquake level and that it is insensitive to the variability of the key parameters.
作者 姜卓尔 王海涛 赵军 史力 Jiang Zhuoer;Wang Haitao;Zhao Jun;Shi Li(Institute of Nuclear and New Energy Technology of Tsinghua University,Beijing,100084,China)
出处 《核动力工程》 EI CAS CSCD 北大核心 2018年第6期53-58,共6页 Nuclear Power Engineering
基金 国家科技重大专项资助项目(ZX069)
关键词 高温气冷堆 反应堆压力容器(RPV)侧向支承 地震易损性 高置信度低失效概率(HCLPF)抗震能力 High temperature gas-cooled reactor Lateral supports of RPV Seismic fragility High Confidence Low Probabilistic Failure (HCLPF )Capacity
  • 相关文献

参考文献2

二级参考文献7

  • 1EPRI.A Methodology for Assessment of Nuclear Power Plant Seismic Margin(Revision 1),final report[R].EPRI NP-6041-SL,August 1991.
  • 2USNRC.Procedural and Submittal Guidance for the Individual Plant Examination of External Events(IPEEE)for Severe Accident Vulnerabilities,final report[R].NUREG-1407,June 1991.
  • 3USNRC.Policy,Technical,and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor(ALWR)Designs[R].Commission Paper SECY-93-087,April 2,1993.
  • 4USNRC.Staff Requirements Memorandom to SECY-93-087[R].July 21,1993.
  • 5USNRC.Interim Staff Guidance on Implementation of a Probabilistic Risk Assessment-Based Seismic Margin Analysis for New Reactors[R].DC/COL-ISG-020.
  • 6ASME.Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications,New York[M].ASME/ANS RA-Sa-2009,2009.
  • 7中国核电工程有限公司.福建福清核电厂1、2号机组抗震裕度评价报告[R].2013.

共引文献2

同被引文献2

引证文献2

二级引证文献3

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部