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An improved multi-unit nuclear plant seismic probabilistic risk assessment approach

机译:一种改进的多单元核电站地震概率风险评估方法

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摘要

This paper proposes an improved approach to external event probabilistic risk assessment for multi-unit sites. It considers unit-to-unit dependencies based on the integration of the copula notion, importance sampling, and parallel Monte Carlo simulation, including their implementation on standard PRA software tools. The multi-unit probabilistic risk assessment (MUPRA) approach and issues related to the current methods for seismic dependencies modeling are discussed. The seismic risk quantification is discussed in the context of two typical numerical schemes: the discretization-based scheme and simulation-based scheme. The issues related to the current discretization-based scheme are also highlighted. To address these issues and to quantify the seismic risk at the site level, an improved approach is developed to quantify the site-level fragilities. The approach is based on a hybrid scheme that involves the simulation-based method to account for the dependencies among the multi-unit structures, systems and components (SSCs) at the group level of dependent SSCs, and the discretization-based scheme. Finally, a case study is developed for the seismic-induced Small Loss of Coolant Accident (SLOCA) for a hypothetical nuclear plant site consisting of two identical advanced (GEN-III) reactor units. The results from this case study summarize the effects of correlation across multiple reactor units on the site-level core damage frequency (CDF). Three multi-unit CDF metrics (site, concurrent and marginal) were calculated for this case study. It is concluded that based on correlations between the SSCs, the total site CDF metric would be the most appropriate multi-unit CDF metric for seismic risk. (C) 2017 Elsevier Ltd. All rights reserved.
机译:本文提出了一种改进的方法,用于多单元站点的外部事件概率风险评估。它基于copula概念,重要性采样和并行Monte Carlo模拟(包括它们在标准PRA软件工具上的实现)的集成来考虑单元间的依赖性。讨论了多单元概率风险评估(MUPRA)方法以及与当前地震依赖建模方法有关的问题。在两个典型的数值方案的背景下讨论了地震风险量化:基于离散化的方案和基于模拟的方案。还强调了与当前基于离散化方案有关的问题。为了解决这些问题并量化站点级别的地震风险,开发了一种改进的方法来量化站点级别的脆弱性。该方法基于一种混合方案,该方案涉及基于仿真的方法,以解决在依赖SSC的组级别上多单元结构,系统和组件(SSC)之间的依赖性,以及基于离散化的方案。最后,针对由两个相同的先进(GEN-III)反应堆单元组成的假想核电站,针对地震引起的冷却液事故小损失(SLOCA)进行了案例研究。该案例研究的结果总结了多个反应堆单元之间的相关性对现场水平堆芯损坏频率(CDF)的影响。针对此案例研究,计算了三个多单元CDF指标(位置,并发和边际)。结论是,基于SSC之间的相关性,总站点CDF指标将是针对地震风险的最合适的多单位CDF指标。 (C)2017 Elsevier Ltd.保留所有权利。

著录项

  • 来源
    《Reliability Engineering & System Safety》 |2018年第3期|34-47|共14页
  • 作者单位

    Univ Maryland, Ctr Risk & Reliabil, College Pk, MD 20742 USA;

    Univ Maryland, Ctr Risk & Reliabil, College Pk, MD 20742 USA;

    Univ Maryland, Ctr Risk & Reliabil, College Pk, MD 20742 USA;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
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