长期热老化后核电站主管道材料的力学行为

钢铁研究学报, 2014, 26(7): 1-7.

长期热老化后核电站主管道材料的力学行为

郑凯 ^1, , 王镇 ^2, , 钟振前 ^3, , 王艳丽 ^4, , 李时磊 ^5,

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.钢铁研究总院国家钢铁材料测试中心,北京100081

4.北京科技大学新金属材料国家重点实验室,北京100083

5.北京科技大学新金属材料国家重点实验室,北京100083

基金项目: 国家高技术研究发展计划资助项目(2012AA050901,2012AA03A507)

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

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

Keywords： cast austenite stainless steel , thermal aging , impact behavior , tensile behavior , fatigue behavior

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.

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材料期刊网

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

参考文献