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Correlation between the stability of irradiation defects and stress corrosion cracking in high temperature water of welded AISI 304 stainless steel

机译:焊接AISI 304不锈钢高温水中辐射缺陷稳定性与应力腐蚀裂缝的相关性

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Stainless steels are used for the fabrication of some internal components of light water cooled reactors, thus being subjected to radiation, heat, and corrosive environment. Neutron irradiation induces different types of damage in stainless steels. As a consequence, these materials may become susceptible to stress corrosion cracking in the high temperature water environment of the reactor cooling circuit. The different types of defects induced by irradiation have been characterised using transmission electron microscopy and positron annihilation. The contribution of the different types of defects (vacancy type clusters, dislocation loops and grain boundary segregation) is assessed by post irradiation annealing treatments. After different time - temperature combinations, the defects are removed, as it is monitored by microscopy and positron annihilation spectroscopy. The removal of defects is correlated to the stress corrosion cracking behaviour of the irradiated material before and after post irradiation annealing.
机译:不锈钢用于制造一些轻水冷却反应器的内部部件,从而进行辐射,热和腐蚀性环境。中子辐射在不锈钢中诱导不同类型的损伤。结果,这些材料可能变得易于在反应器冷却回路的高温水环境中应力腐蚀裂缝。使用透射电子显微镜和正电子湮灭表征通过辐射引起的不同类型的缺陷。通过后照射退火处理评估不同类型的缺陷(空位类型簇,位错环和晶界偏析)的贡献。不同时间之后 - 温度组合,缺陷被移除,因为它是由显微镜和正电子湮没光谱监测。去除缺陷在照射退火前后辐照材料的应力腐蚀开裂行为相关。

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