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Radiation-induced degradation of stainless steel light water reactor internals

机译：辐射引起的不锈钢轻水反应堆内部零件的降解

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摘要

In order to provide a scientific basis for proposed life extension of current light water reactors, the radiation-induced degradation of stainless steel reactor internals will be discussed. A brief review of the basic radiation damage effects in stainless steels at LWR relevant conditions will be presented. It will be discussed how these basic effects result in the key degradation modes that have been identified by light water reactor experience to date, as well as the possibility for more severe degradation or new forms of degradation under extended service conditions. The forms of degradation that will be discussed include radiation hardening, embrittlement, dimensional stability (e.g., creep and swelling), radiation-induced segregation and precipitation, transmutation effects and irradiation-induced stress corrosion cracking.
机译：为了为目前的轻水反应堆的使用寿命延长提供科学依据，将讨论辐射引起的不锈钢反应堆内部部件的降解。将简要介绍在轻水堆相关条件下不锈钢的基本辐射损伤效应。将讨论这些基本影响如何导致迄今为止轻水反应堆经验已确定的关键降解模式，以及在延长使用条件下可能出现更严重的降解或新的降解形式的可能性。将要讨论的降解形式包括辐射硬化，脆化，尺寸稳定性（例如蠕变和膨胀），辐射诱导的偏析和沉淀，trans变效应以及辐射诱导的应力腐蚀开裂。

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