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首页> 外文期刊>Transactions of the American nuclear society >I-PRA Uncertainty Importance Ranking to Enhance Fire PRA Realism for Nuclear Power Plants
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I-PRA Uncertainty Importance Ranking to Enhance Fire PRA Realism for Nuclear Power Plants

机译:I-PRA不确定性重要性排名,以增强核电站的火灾PRA现实主义

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摘要

State-of-the-art methodologies, tools, and data for Fire PRA of Nuclear Power Plants (NPPs) are documented in NUREG/CR-6850, hereinafter the "current methodology." Despite recent advances in Fire PRA research and implementation, the current methodology can still lead to risk overestimation due to use of excessively conservative input parameters and assumptions [1]. Lack of realism in Fire PRA may mask identification of critical risk-contributing factors and result in unnecessary and costly plant modifications. To better facilitate risk-informed decision-making, the degree of realism in Fire PRA should be improved.There have been studies that utilized dynamic PRA approaches for improving the realism of the current Fire PRA methodology. These studies, however, have had challenges in areas such as (i) completeness in exploration of the solution space, (ⅱ) aggregation, interpretation, and communication of the large volume of outputs, and (ⅲ) validation of dynamic accident scenarios and underlying physical models. Furthermore, due to the widespread use of classical PRA by the nuclear industry and regulatory agency, the transition to a fully dynamic PRA would require a significant investment of resources. As a more feasible alternative, the Integrated PRA (I-PRA) methodology [1] has been developed by some of the authors of this paper.
机译:在Nureg / CR-6850中记录了核电厂(NPPS)的最先进的方法,工具和核电厂(NPP)的火灾PRA数据,下文中称为“电流方法”。尽管最近的火灾PRA研究和实施进展,但目前的方法仍可导致由于使用过保守的输入参数和假设而导致风险高估[1]。在火灾中缺乏现实主义可能会掩盖危急风险贡献因素的识别,导致不必要和昂贵的植物修改。为了更好地促进风险明智的决策,应该改善火灾前的现实程度。一直在研究,利用动态PRA方法改善当前火灾PRA方法的现实主义。然而,这些研究在诸如(i)探索的地区(i)勘探空间的完整性挑战,(Ⅱ)大量产出的汇总,解释和沟通,以及(Ⅲ)动态事故情景和潜在的验证物理模型。此外,由于核工业和监管机构的古典PRA广泛使用,转型至完全动态的PRA将需要大量资源投资。作为一种更可行的替代方案,集成的PRA(I-PRA)方法[1]是由本文的一些作者开发的。

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  • 来源
    《Transactions of the American nuclear society》 |2020年第11期|967-970|共4页
  • 作者单位

    Socio-Technical Risk Analysis (SoTeRiA) Laboratory Department of Nuclear Plasma and Radiological Engineering Grainger College of Engineering University of Illinois at Urbana-Champaign (UIUC) 104 S Wright St. Urbana IL 61801 USA SoTeRiA Industry Affiliates Program (SoTeRiA-lAP) Grainger College of Engineering UIUC Urbana IL USA;

    Socio-Technical Risk Analysis (SoTeRiA) Laboratory Department of Nuclear Plasma and Radiological Engineering Grainger College of Engineering University of Illinois at Urbana-Champaign (UIUC) 104 S Wright St. Urbana IL 61801 USA SoTeRiA Industry Affiliates Program (SoTeRiA-lAP) Grainger College of Engineering UIUC Urbana IL USA;

    Socio-Technical Risk Analysis (SoTeRiA) Laboratory Department of Nuclear Plasma and Radiological Engineering Grainger College of Engineering University of Illinois at Urbana-Champaign (UIUC) 104 S Wright St. Urbana IL 61801 USA SoTeRiA Industry Affiliates Program (SoTeRiA-lAP) Grainger College of Engineering UIUC Urbana IL USA;

    Idaho National Laboratory Idaho Falls. ID 83415 USA;

    Socio-Technical Risk Analysis (SoTeRiA) Laboratory Department of Nuclear Plasma and Radiological Engineering Grainger College of Engineering University of Illinois at Urbana-Champaign (UIUC) 104 S Wright St. Urbana IL 61801 USA SoTeRiA Industry Affiliates Program (SoTeRiA-lAP) Grainger College of Engineering UIUC Urbana IL USA Beckman Institute for Advanced Science and Technology UIUC Urbana IL USA;

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