钠冷快堆堆容器堆内构件用316型不锈钢及其持久断裂性能  

Type 316 austenitic steels for reactor vessel and internals in sodium fast reactors and their creep rupture properties

作　　者：燕春光 李雅平[1] 王明政[1] YAN Chun-guang;LI Ya-ping;WANG Ming-zheng(Division of Reactor Engineering Technology Research,China Institute of Atomic Energy,Beijing 102413,China)

机构地区：[1]中国原子能科学研究院反应堆工程技术研究部,北京102413

出　　处：《钢铁研究学报》2018年第12期935-942,共8页Journal of Iron and Steel Research

基　　金：国家自然科学基金青年科学基金资助项目(11705286).

摘　　要：316型不锈钢用于钠冷快堆堆容器堆内构件的制造已成为各发展快堆国家的共识,如何提高持久断裂性能成为快堆用316型不锈钢的研究重点。概述了316型不锈钢在国外快堆中的应用现状,总结了成分(C、N、Mo、P)、组织(晶粒度和铁素体)及环境介质(中子辐照环境和高温钠介质)等因素对其持久强度和持久伸长率的影响规律和机理,介绍了目前中国示范快堆用316不锈钢的发展现状,最后提出了快堆用316不锈钢的发展建议。The type 316 stainless steels (316ss)are widely used as structural materials for reactor vessel and internals in sodium fast reactors (SFRs),which are agreed by designers of SFRs all over the world.Creep rupture properties become one of the important properties of the 316ss.The application of 316ss in fast reactors at abroad was briefly reviewed.Then the effect of alloying elements,microstructure and environmental media like neutron irradiation and sodium on creep rupture properties was summarized.More specifically,the alloying elements consist of carbon,nitrogen,molybdenum and phosphorus,while the microstructure consists of grain size and ferrite content.Finally,the current development status of 316ss for demonstration fast reactors in China was introduced. Furthermore,some suggestions were also proposed.

关 键 词：316型不锈钢 钠冷快堆 持久强度 持久塑性 

分 类 号：TL1[核科学技术—核能科学] TG142.71[一般工业技术—材料科学与工程]