Abstract Existing elastic analysis methods cannot be adhered to in order to assess the structural integrity of a reactor vessel and internals for a beyond design basis earthquake. Elasto-plastic analysis methods are required, and the factors that affect the elasto-plastic behavior of reactor materials should be taken into account. In this study, a material behavior model was developed that considers the irradiation embrittlement effect, which affects the elasto-plastic behavior of the reactor material. This was used to perform the elasto-plastic time history analyses of the reactor vessel and its internals for beyond design basis earthquake. For this investigation, appropriate beyond design basis earthquakes and reliable finite element models were used. Based on the analysis results, consideration was given to the load reduction effect and the margin change. These were transferred to the internals due to the plastic deformation of the reactor vessel.

中文翻译：

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使用弹塑性时程分析研究超设计基础地震反应堆容器和内部构件的地震响应

摘要 不能坚持现有的弹性分析方法来评估超设计基准地震的反应堆容器和内部构件的结构完整性。需要采用弹塑性分析方法，并考虑影响反应器材料弹塑性行为的因素。在这项研究中，开发了一种材料行为模型，该模型考虑了影响反应堆材料弹塑性行为的辐射脆化效应。这用于对反应堆容器及其内部构件进行弹塑性时程分析，以应对超设计基准地震。在本次调查中，使用了适当的超设计基准地震和可靠的有限元模型。根据分析结果，考虑了减载效果和裕度变化。由于反应堆容器的塑性变形，这些被转移到内部构件上。