摘要
介绍了核反应堆容器用SA508-3钢锻件试样,经历不同的模拟焊后热处理工艺后,组织变化导致低温韧性下降,并分析了其原因。
This paper introduces the SA508-3 steel forgings for nuclear reactor vessels. After different simulated post-weld heat treatment processes,the microstructure changes lead to the decrease of low temperature toughness,and the reasons have been analyzed.
出处
《大型铸锻件》
2019年第6期25-27,共3页
Heavy Casting and Forging
关键词
SA508-3钢
锻件
模拟焊后热处理
冲击韧性
组织
SA508-3 steel
forging
simulated post-weld heat treatment
impact toughness
microstructure
