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Development of level-1 PSA method applicable to Japan Sodium-cooled Fast Reactor

机译：开发适用于日本钠冷快堆的1级PSA方法

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摘要

This paper describes a study to develop the level-1 probabilistic safety assessment (PSA) method that is applicable to the Japan Sodium-cooled Fast Reactor (JSFR). This study has been started since August 2010 and aims to provide a new evaluation method of (1) passive safety architectures related to internal events and (2) an advanced seismic isolation system related to a seismic event as a representative external event in Japan. Regarding the internal events evaluation, a quantitative analysis on the frequency of the core damage caused by reactor shutdown failure was conducted. A failure in passive reactor shutdown was taken into account in the event tree model. The failure rate of sodium-cooled fast reactor (SFR) specific components was evaluated based on the operating experience in existing SFRs by applying the Hierarchical Bayesian Method, which can consider a plant-to-plant variability. By conducting an uncertainty analysis, it was found that the assumption about the correlation of the probability parameters between the main and backup reactor shutdown systems (RSSs) is sensitive to the mean value of the frequency of the core damage caused by reactor shutdown failure. As for the seismic event evaluation, seismic response analysis and sensitivity analysis of a seismic isolation system were carried out. Rubber bearings have a hardening property in horizontal direction and a softening property in vertical direction in case of large deformation. Therefore the analyses considered nonlinearity of rubber bearings. Both horizontal and vertical nonlinear characteristics of rubber bearings were explained by multi-linear model. Mass point analytical models were applied. At first, seismic response analysis was executed in order to investigate influence of nonlinearity of rubber bearing upon response of building. Then sensitivity analysis was executed. Parameters of rubber bearings, oil dampers and the building were fluctuated, and influence of dispersion of these parameters upon response of building was investigated. As a result, it was confirmed that nonlinear properties of rubber bearings have influence on response of the building and inner equipment.
机译：本文描述了一项研究，旨在开发适用于日本钠冷快堆（JSFR）的1级概率安全评估（PSA）方法。这项研究自2010年8月开始，旨在提供一种新的评估方法，用于（1）与内部事件有关的被动安全体系结构和（2）与在日本具有代表性的外部地震事件有关的高级地震隔离系统。关于内部事件评估，对反应堆关闭故障引起的堆芯损坏的频率进行了定量分析。在事件树模型中考虑了被动反应堆关闭故障。钠冷却快堆（SFR）特定组件的故障率是根据现有SFR的运行经验通过应用分级贝叶斯方法评估的，该方法可以考虑工厂之间的差异。通过进行不确定性分析，发现关于主反应堆和备用反应堆停堆系统（RSS）之间的概率参数相关性的假设对由反应堆停堆故障引起的堆芯损坏频率的平均值敏感。对于地震事件评估，进行了隔震系统的地震响应分析和敏感性分析。橡胶轴承在大变形的情况下具有水平方向的硬化性能和垂直方向的软化特性。因此，分析考虑了橡胶轴承的非线性。用多线性模型解释了橡胶轴承的水平和垂直非线性特性。应用了质点分析模型。首先，进行地震响应分析，以研究橡胶轴承非线性对建筑物响应的影响。然后进行敏感性分析。橡胶轴承，减震器和建筑物的参数发生波动，并研究了这些参数的离散度对建筑物响应的影响。结果，证实了橡胶轴承的非线性特性会影响建筑物和内部设备的响应。

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  • 来源
    《Nuclear Engineering and Design》 |2014年第4期|268-280|共13页
  • 作者

    K. Kurisaka; T. Sakai; H. Yamano; S. Fujita; K. Minagawa; A. Yamaguchi; T. Takata;

  • 作者单位

    Advanced Nuclear System R&D Directorate, Japan Atomic Energy Agency, Ibaraki,Japan;

    Advanced Nuclear System R&D Directorate, Japan Atomic Energy Agency, Ibaraki,Japan;

    Advanced Nuclear System R&D Directorate, Japan Atomic Energy Agency, Ibaraki,Japan;

    Department of Mechanical Engineering, School of Engineering, Tokyo Denki University, Tokyo, Japan;

    Department of Mechanical Engineering, School of Engineering, Tokyo Denki University, Tokyo, Japan;

    Department of Energy and Environment Engineering, Osaka University, Osaka, Japan;

    Department of Energy and Environment Engineering, Osaka University, Osaka, Japan;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
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