摘要
以生产实践和文献资料为基础,研究核反应堆容器用SA508Gr.3钢大锻件的热处理工艺,分析SA508Gr.3钢化学成分、热处理工艺、微观组织和力学性能之间的定性关系,指出核电大锻件现有热处理过程中存在的问题及解决思路。
An investigation was conducted into the heat treatment processes of SA508Gr.3 steel used for nuclear power reactor pressure vessels according to manufacturing practice and previous academical research in literature. Relationship among chemical composition-heat treatment processes-microstructure-meehanical properties were analyzed qualitatively. It points out the problems existed in the coupe of heat treatment of large forgings for nuclear power plant at present and appropriate resolution.
出处
《一重技术》
2015年第3期49-52,39,共5页
CFHI Technology
