反应堆压力容器特厚锻件制造及性能研究  

Study on Manufacture and Properties of Extra-thick Forgings for Reactor Pressure Vessel

作　　者：陈海波[1] 罗英[1] 王小彬[1] 尹祁伟[1] 

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,四川成都610041

出　　处：《热加工工艺》2016年第7期164-166,170,共4页Hot Working Technology

摘　　要：采用双真空冶炼浇注工艺和镦粗、拔长与局部延展相结合的锻造工艺以及优化的热处理工艺参数,制造了反应堆压力容器特厚锻件试验件,并对试验件进行了全截面取样,进行了强度、冲击功及无塑性转变温度测试。结果表明:锻件各项性能满足RCC-M规范要求,锻件强度的截面效应较小,冲击功及无塑性转变温度的截面效应较大。Extra-thick forgings for reactor vessel were made by using vacuum smelting and casting process, forging technology of upsetting combined stretching with local extension, and optimized heat treatment process. The whole section of the test specimen was also sampled. Strength, impact energy, and nil-ductility transition temperature were tested. The results show that the properties of the forgings meet the requirements of RCC-M specification. The section effect of the strength of the forging is smaller, and the section effect of impact energy and nil-ductility transition temperature arc larger.

关 键 词：反应堆压力容器 厚壁锻件 性能 

分 类 号：TG316[金属学及工艺—金属压力加工]