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THERMAL AGING PERFORMANCE OF DOMESTIC CAST AUSTENITIC STAINLESS STEELS IN NUCLEAR POWER PLANTS

机译:核电站国内铸造奥氏体不锈钢的热老化性能

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The domestic cast austenitic stainless steels (CASS) used for PWR main coolant lines face thermal aging phenomenon during long-term service at reactor operating temperatures in the range of 280-320°C. The accelerated thermal aging experiment of CASS at an elevated temperature of 400°C was carried out. The decrease regularity of absorbed energy of CASS at room temperature was obtained by Charpy impact test, and the variation trend of impacted specimen's fracture surfaces of CASS at different aging time was observed by scanning electron microscope. The experimental results show that: after 15,000 hours of accelerated thermal aging, the domestic CASS gradually reaches a thermal aging saturation, and its absorbed energy suffers a dramatic loss, dropping to almost 41-45% of the initial value, but still meets the assessment indicators for unaged state required by design specifications.
机译:国内铸造奥氏体不锈钢(CASS)用于PWR主冷却液在长期服务期间的热老化现象,在反应堆工作温度范围内的280-320℃。进行400℃的高温下的CASS加速热老化实验。通过夏比冲击试验获得室温下的CAS的吸收能量的规律性,并且通过扫描电子显微镜观察到在不同老化时间下的CASS裂缝表面的变化趋势。实验结果表明:在15000小时的加速热老化后,国内CASS逐渐达到热老化饱和度,其吸收能量遭受了剧烈损失,降至初始价值的近41-45%,但仍然达到评估设计规范所需的未定状态指标。

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