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Review and categorization of existing studies on the estimation of probabilistic failure metrics for Reactor Coolant Pressure Boundary piping and steam generator tubes in Nuclear Power Plants

机译:核电站蓄电池压力边界管道和蒸汽发生器管概率故障指标估计现有研究的审查与分类

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This paper presents the first output of the International Atomic Energy Agency (IAEA) Coordinated Research Project (CRP), titled Methodology for Assessing Pipe Failure Rates in Advanced Water-Cooled Reactors (AWCRs), launched in 2018. This IAEA CRP is aimed at developing a good-practices document for estimating the probabilistic failure metrics of piping in AWCRs. The reliability of piping that comprise the Reactor Coolant Pressure Boundary (RCPB) is important for maintaining safe and stable operations of Nuclear Power Plants (NPPs) because failure of those piping components could lead to undesirable consequences, such as plant shutdown, costly repair, the occurrence of Loss-of-Coolant Accidents (LOCAs) and, possibly, subsequent core damage or large release events. Probabilistic failure metrics (e.g., failure rate, failure frequency, or failure probability) of RCPB components are the key inputs to the Probabilistic Safety/Risk Assessment (PSA/PRA) and risk management of NPPs. The estimation of probabilistic failure metrics, however, is challenging, especially for AWCRs, due to the lack of operating experience. Therefore, as the first step of the IAEA CRP activities, this paper is developed to provide a literature review of the existing studies (from 2000 to April 2019) on the estimation of probabilistic failure metrics for RCPB piping and Steam Generator (SG) tubes of NPPs and to categorize them based on four criteria: (1) explicitness of incorporation of physical failure mechanisms; (2) types of failure characterization; (3) types of physical models for degradation; and (4) explicitness of consideration of maintenance. The existing studies are also analyzed from the viewpoint of the following key aspects: (i) uncertainty analysis, (ii) sensitivity analysis, (iii) validation strategies, and (iv) the areas of applications.
机译:本文介绍了国际原理能源机构(原子能机构)协调研究项目(CRP)的第一个产出,标题为2018年推出的先进水冷反应堆(AWCR)中的管道故障率的方法。此IAEA CRP旨在发展一种良好的练习文件,用于估算AWCR中的管道概率故障指标。包括反应器冷却剂压力边界(RCPB)的管道的可靠性对于维持核电厂(NPPS)的安全和稳定操作是重要的,因为这些管道部件的失败可能导致不良后果,例如工厂关闭,昂贵的修复发生冷却损失事故(基因座),可能是随后的核心损坏或大释放事件发生。 RCPB组件的概率故障指标(例如,故障率,故障频率或故障频率)是概率安全/风险评估(PSA / PRA)和NPPS风险管理的关键输入。然而,由于缺乏运营经验,对概率故障指标的估计是具有挑战性的,特别是对于AWCRS。因此,作为原子能机构CRP活动的第一步,开发了该论文,为现有研究(从2000年至2019年4月)提供了关于RCPB管道和蒸汽发生器(SG)管的概率故障指标的文献综述NPPS并根据四个标准对其进行分类:(1)掺入物理失败机制的明确性; (2)故障表征类型; (3)劣化的物理模型类型; (4)考虑维护的明确性。从以下关键方面的观点出发,还分析了现有的研究:(i)不确定性分析,(ii)敏感性分析,(iii)验证策略和(iv)申请领域。

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