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The Study on the Fatigue Damage Estimation Method for the Buckled Reactor Vessel under Earthquake Loading

机译:地震载荷下屈曲反应器血管疲劳损伤估计方法研究

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An estimation of fatigue damage derived from buckling deformation is one of the important factor to evaluate a safety margin of seismic design criteria for thin walled fast breeder reactor components, in addition to estimate the critical buckling strength itself. Post-buckling waves obtained by seismic response analyses of SDOF ( Single Degree of Freedom ) models were analyzed as displacement range-frequency histogram. Cyclic post buckling fatigue tests were performed with 304 S.S cylinders to obtain basic fracture data and to simulate the seismic response characteristic with the static approach. Fatigue damage estimation methods were discussed with the correlation to the maximum global displacement response.
机译:避免屈曲变形的疲劳损伤的估计是评估薄壁快速育种反应器组分的地震设计标准的安全裕度的重要因素之一,除了估计临界屈曲强度本身。通过SDOF的地震反应分析获得的后屈曲波(单一自由度)模型被分析为位移范围频率直方图。用304秒的气缸进行循环后屈曲疲劳试验,以获得基本的骨折数据,并用静态方法模拟地震响应特性。疲劳损伤估计方法与最大全球位移响应的相关性讨论。

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