压水堆核电站主管道材料的低周疲劳行为研究  

LOW CYCLE FATIGUE BEHAVIOR OF PWR PRIMARY PIPE MATERIAL FOR NUCLEAR POWER PLANT

作　　者：薛飞[1] 余伟炜[1] 遆文新[1] 王兆希[1,2] 张路[1] 林磊[1] 石崇哲[3] 

机构地区：[1]苏州热工研究院,苏州215004 [2]清华大学材料科学与工程系,北京100084 [3]西安工业大学材料与化工学院,西安71003

出　　处：《机械强度》2011年第6期890-894,共5页Journal of Mechanical Strength

基　　金：国家863计划项目(2008AA031701-3);中国博士后科学基金(20090450161)资助~~

摘　　要：对压水堆核电站主管道材料Z3CN20.09M进行室温与350℃低周疲劳性能试验,得到材料循环变形规律和寿命演化模型。结果表明,主管道材料表现为先强化后软化的循环特性,但强化的程度取决于温度和应变幅;当应变幅较大时,高温疲劳断裂寿命高于室温疲劳断裂寿命,但随着应变幅的降低,二者的疲劳断裂寿命差别逐渐减小。常温与350℃高温疲劳断口的分析表明,Z3CN20.09M钢低周疲劳裂纹呈凸形扩展,并伴随有疲劳辉纹出现。A serial of low cycle fatigue tests for native PWR（pressurized-water reactor） primary pipe material of nuclear power plant under room temperature and elevated temperature of 350 ℃ were carried out.Based on the test results,the cyclic behavior and fatigue life are obtained.Mainly,the primary pipe material exhibits an initial hardening followed by softening,and the hardening amount depends on the temperature and loading strain;the fatigue life generally increases with an increase in testing temperature when the strain range is large,as the decreasing of strain amplitude,temperature effect impaired gradually.Microstructure features were discussed to the low cycle fatigue specimens,the results show that the fatigue crack expends in a convex mode accompanied with some wavy fatigue striations.

关 键 词：低周疲劳 核电 压水堆 主管道 

分 类 号：O346.2[理学—固体力学]