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Probabilistic Safety Criteria and Core Degradation Mechanism

机译:概率安全标准和核心退化机制

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As nuclear power plant age, degradation of structure, systems and components can be expected to occur. The understanding of the effect of the age related degradation is important to ensure safe operation of the nuclear power plant. The pressure tubes in CANDU reactors are critical components and its failure has consequences of concern. These cold worked Zr-2.5% Nb pressure tubes may degrade due to ageing mechanisms like creep and delayed hydride cracking. It is important to periodically monitor the serviceability these tubes over the service life. This paper discusses the estimation of the allowable conditional failure probability of the pressure tubes for meeting the risk informed regulation criteria of the US-NRC regulatory guide RG. 1.174.
机译:随着核电站的老化,结构,系统和组件的退化可能会发生。了解与年龄有关的退化的影响对于确保核电厂的安全运行非常重要。 CANDU反应堆中的压力管是关键组件,其故障会引起关注。这些经过冷加工的Zr-2.5%Nb压力管可能会由于蠕变和氢化物延迟开裂等老化机制而退化。重要的是在使用寿命内定期监视这些管的可维修性。本文讨论了满足US-NRC监管指南RG的风险告知监管标准的压力管允许的条件性失效概率的估计。 1.174。

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