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Procedure for assessment of WWER reactor pressure vessel materials degradation

机译:评估WWER反应器压力容器材料降解的程序

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The paper describes a new procedure prepared for assessment of reactor pressure vessel materials degradation of WWER type reactors in the Czech Republic.This procedure has been prepared within activities of the Czech Association of Mechanical Engineers (ASI) and represents a part of the global procedure for assessment of WWER component lifetime.This procedure takes into account possible damaging mechanisms and their consequences in material property changes. Fracture mechanics approach is applied using "critical temperature of brittleness" as a "reference temperature". Transition temperatureshifts are determined not only from Charpy impact notch toughness tests, but also from static and dynamic fracture toughness tests.Surveillance specimens programs of Czech WWER reactors have been designed and/or modified to comply these requirements.
机译:本文描述了一种用于评估反应器压力容器材料在捷克共和国的Wwer型反应器的降解的新方法。该程序已在捷克机械工程师(ASI)的活动中编写,并代表了全球程序的一部分评估WWER组件寿命。本程序考虑了可能的破坏机制及其在材料财产变化中的后果。使用“临界温度”作为“参考温度”施加裂缝力学方法。过渡温度不仅确定夏比冲击缺口韧性试验,而且从静态和动态断裂韧性试验中确定。捷克WWER反应器的抗震标本计划已经设计和/或修改以遵守这些要求。

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