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Effects of thermal aging on microstructure and hardness of stainless steel weld-overlay claddings of nuclear reactor pressure vessels

机译:热老化对核反应堆压力容器不锈钢堆焊层组织和硬度的影响

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The effects of thermal aging of stainless steel weld-overlay claddings of nuclear reactor pressure vessels on the microstructure and hardness of the claddings were investigated using atom probe tomography and nanoindentation testing. The claddings were aged at 400 ?C for periods of 100–10,000 h. The fluctuation in Cr concentration in the δ-ferrite phase, which was caused by spinodal decomposition, progressed rapidly after aging for 100 h, and gradually for aging durations greater than 1000 h. On the other hand, NiSiMn clusters, initially formed after aging for less than 1000 h, had the highest number density after aging for 2000 h, and coarsened after aging for 10,000 h. The hardness of the δ-ferrite phase also increased rapidly for short period of aging, and saturated after aging for longer than 1000 h. This trend was similar to the observed Cr fluctuation concentration, but different from the trend seen in the formation of the NiSiMn clusters. These results strongly suggest that the primary factor responsible for the hardening of the δ-ferrite phase owing to thermal aging is Cr spinodal decomposition.
机译:利用原子探针层析成像和纳米压痕试验,研究了核反应堆压力容器不锈钢堆焊层的热老化对层组织和硬度的影响。包层在400°C时效100–10,000 h。 δ形铁素体相中Cr浓度的波动是由旋节线分解引起的,在时效100 h后迅速发展,并在时效持续时间大于1000 h时逐渐变化。另一方面,NiSiMn团簇在时效少于1000h后最初形成,在时效2000h后具有最高的数密度,并在时效10,000h后变粗。 δ铁素体相的硬度在短时效期间也迅速增加,并且在超过1000小时的时效后达到饱和。该趋势与观察到的Cr波动浓度相似,但是与NiSiMn团簇形成中所看到的趋势不同。这些结果强烈表明,归因于热时效而导致δ铁素体相硬化的主要因素是Cr旋节线分解。

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