Impact of structural aging on seismic risk assessment of reinforced concrete structures in nuclear power plants
Impact of structural aging on seismic risk assessment of reinforced concrete structures in nuclear power plants
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结构老化对核电站钢筋混凝土结构地震风险评估的影响
DOI：
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发表时间：
1996
期刊：
影响因子：
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通讯作者：
J. Song
中科院分区：
文献类型：
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作者：
B. Ellingwood;J. Song
结构老化计划旨在解决核电厂混凝土结构部件和系统由于老化和侵蚀性环境压力而随时间推移而退化的可能性。结构在正常运行条件下是被动的，但在减轻设计基础事件方面发挥着关键作用，特别是那些由地震，极端风，火灾和洪水等外部挑战引起的事件。结构是工厂特有的，独特的，通常很难检查，几乎不可能更换。结构故障在事故缓解中的重要性被放大，因为这种故障可能导致其他部件的共因故障。结构状况评估和使用寿命预测必须集中在工厂内的一些关键部件和系统上。构成风险的主要因素和需要特别注意的组件和系统可以通过概率风险评估（PRA）的数学形式来识别。为了说明，结构退化的作用，由于老化对工厂的风险进行检查，通过一个核电厂的1级地震PRA的框架。结构退化的合理机制被发现增加核心损坏的概率约为2倍。
The Structural Aging Program is addressing the potential for degradation of concrete structural components and systems in nuclear power plants over time due to aging and aggressive environmental stressors. Structures are passive under normal operating conditions but play a key role in mitigating design-basis events, particularly those arising from external challenges such as earthquakes, extreme winds, fires and floods. Structures are plant-specific and unique, often are difficult to inspect, and are virtually impossible to replace. The importance of structural failures in accident mitigation is amplified because such failures may lead to common-cause failures of other components. Structural condition assessment and service life prediction must focus on a few critical components and systems within the plant. Components and systems that are dominant contributors to risk and that require particular attention can be identified through the mathematical formalism of a probabilistic risk assessment, or PRA. To illustrate, the role of structural degradation due to aging on plant risk is examined through the framework of a Level 1 seismic PRA of a nuclear power plant. Plausible mechanisms of structural degradation are found to increase the core damage probability by approximately a factor of two.