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An approach to the construction of a one top fire event PSA model

机译:一种顶级火灾事件PSA模型的构建方法

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摘要

An internal fire event probabilistic safety assessment (PSA) model has been generally quantified by modifications of a pre-developed internal events PSA model. New accident sequence logics not covered in the internal events PSA model are separately developed to incorporate them into the fire PSA model. Previous studies on the changes of the one top internal event PSA model for the one top fire event PSA model have been limited to the equipment failures affected by the fire. In addition, they assumed that the probabilities of basic events associated with equipment or cables impacted by the fire are one. However, the probabilities of spurious operation events and human failure events affected by the fire might not be estimated as one. In this study, new modification rules were proposed for the construction of a one top PSA model for fire events by using a one top internal event PSA model. The proposed new modification rules can be applied to all the fire damage events for the fire-induced equipment failure events and spurious operation events, human error events impacted by a fire, regardless of whether they are estimated as one or not. Applications of the proposed modification rules to the compartment and scenario-level fires for the hypothetical plants were performed for demonstrating their appropriateness to the changes of the one top internal event PSA model to the one top fire event PSA model. In addition, quantification procedure with the one top fire event PSA model was presented and discussed.
机译:内部火灾事件概率安全评估(PSA)模型通常通过修改预先开发的内部事件PSA模型进行量化。内部事件PSA模型中未涵盖的新事故序列逻辑将单独开发,以将其合并到火灾PSA模型中。先前对一种最高火灾事件PSA模型的一种最高内部事件PSA模型的更改的研究仅限于受火灾影响的设备故障。此外,他们假设与设备或电缆受火灾影响相关的基本事件的概率是一个。但是,受火灾影响的虚假操作事件和人为失误事件的概率可能不会被估计为一。在这项研究中,提出了一种新的修改规则,用于通过使用一个顶部内部事件PSA模型来构建火灾事件的一个顶部PSA模型。所提出的新的修改规则可以应用于由火灾引起的设备故障事件和虚假操作事件,受火灾影响的人为错误事件的所有火灾损坏事件,无论它们是否被估计为是。进行了拟议的修改规则在假设工厂的车厢和情景级别火灾中的应用,以证明其适用于将一个最高内部事件PSA模型更改为一个最高火灾事件PSA模型。此外,还提出并讨论了使用一个顶部火灾事件PSA模型的量化程序。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2009年第11期|2514-2520|共7页
  • 作者单位

    Integrated Safety Assessment Division, Korea Atomic Energy Research Institute, 1045 Daedeokdaero (150 Deokjin-Dong), Yuseong-Gu, Daejon 305-353, Republic of Korea;

    Integrated Safety Assessment Division, Korea Atomic Energy Research Institute, 1045 Daedeokdaero (150 Deokjin-Dong), Yuseong-Gu, Daejon 305-353, Republic of Korea;

    Integrated Safety Assessment Division, Korea Atomic Energy Research Institute, 1045 Daedeokdaero (150 Deokjin-Dong), Yuseong-Gu, Daejon 305-353, Republic of Korea;

  • 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
  • 中图分类
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