长期热老化后核电站主管道材料的力学行为  

Mechanical Behavior of Long-Term Thermal Aged Nuclear Power Plant′s Primary Circuit Pipes

作　　者：郑凯[1] 王镇[2] 钟振前[1] 王艳丽[3] 李时磊[3] 

机构地区：[1]钢铁研究总院国家钢铁材料测试中心,北京100081 [2]钢铁研究总院科技信息与战略研究所,北京100081 [3]北京科技大学新金属材料国家重点实验室,北京100083

出　　处：《钢铁研究学报》2014年第7期1-7,共7页Journal of Iron and Steel Research

基　　金：国家高技术研究发展计划资助项目(2012AA050901;2012AA03A507)

摘　　要：大型压水堆核电站主管道多采用综合性能优良的铸造奥氏体不锈钢,但该材料在中温下长期服役会发生热老化脆化现象。总结了国内外的最新研究成果,主要综述了长期热老化过程中主管道材料的相变规律及其影响因素,以及长期热老化后材料的纳米硬度、拉伸、冲击和疲劳行为。Cast austenite stainless steels （CASS） are widely used in the primary circuit piping of pressurized water nuclear reactors for their excellent mechanical behavior, corrosion resistance and good weldability. But, cast aus- tenite stainless steels have a tendency of thermal aging embrittlement after long term service at mid-temperature （280- 320 ℃）. The latest research results were summarized, mainly including the phase transformation rules and its influence factors during long-term thermal aging, the nano hardness, tensile, impact and fatigue behavior of CASS after long-term thermal aging.

关 键 词：铸造奥氏体不锈钢 热老化 冲击行为 拉伸行为 疲劳行为 

分 类 号：TL353.11[核科学技术—核技术及应用]