首页> 外文会议>ICAPP 2008;International conference on advances in nuclear power plants >Mechanism-based Ageing Management of Primary Water Stress Corrosion Cracking of Ni-base Components in PWR Environments
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Mechanism-based Ageing Management of Primary Water Stress Corrosion Cracking of Ni-base Components in PWR Environments

机译:压水堆环境中镍基成分一次水应力腐蚀开裂的基于机理的时效管理

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Material aging is a principle cause for the aging of engineering systems that can lead to reduction in reliability and continued safety and increase in the cost of operation and maintenance. As the nuclear power plants get older, aging becomes an issue, because aging degradation can affect the structural integrity of systems and components in the same manner. To ensure the safe operation of nuclear power plants, it is essential to assess the effects of age-related degradation of plant structures, systems, and components. In this paper, a mechanistically based probabilistic approach is reviewed as a framework for this material aging degradation of NPPs. For the first level modeling of this process, the EAC-induced failure process, is one of the main degradation processes of nickel-based alloys in the pressurized water reactor environments, has examined the effect of uncertainties in key parameters in models for EAC, fracture and inspection, based on a sensitivity study.
机译:材料老化是工程系统老化的主要原因,这可能导致可靠性降低和持续的安全性下降,并增加运行和维护成本。随着核电厂的老化,老化成为一个问题,因为老化退化会以相同的方式影响系统和组件的结构完整性。为了确保核电厂的安全运行,必须评估与年龄有关的电厂结构,系统和组件的退化所带来的影响。在本文中,将基于机械的概率方法作为该NPPs物质老化降解的框架进行了综述。对于此过程的第一级建模,EAC诱发的失效过程是压水反应堆环境中镍基合金的主要降解过程之一,已经检查了EAC模型中关键参数的不确定性,断裂的影响。并根据敏感性研究进行检查。

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