国产压水堆核电站机组主管道疲劳裂纹扩展特性实验研究  

Experiment Study on Fatigue Crack Propagation Behavior of Primary Pipe in China Pressurized-water Reactor

作　　者：薛飞[1] 余伟炜[2] 蒙新明[2] 王兆希[2] 刘伟[1] 束国刚 

机构地区：[1]清华大学材料科学与工程系,北京市海淀区100084 [2]苏州热工研究院有限公司,江苏省苏州市215004 [3]中广核工程有限公司,广东省深圳市518124

出　　处：《中国电机工程学报》2014年第8期1310-1317,共8页Proceedings of the CSEE

基　　金：国家重点基础研究发展计划项目(973计划)(2011CB610506);国家科技重大专项项目(2011ZX06004002)~~

摘　　要：在室温条件下,对国产压水堆核电站主管道母材及其TIG接头试样进行疲劳裂纹扩展试验,并采用光学显微镜观测裂纹扩展路径,结合扫描电镜观察试样断口微观形貌。试验结果显示TIG接头的裂纹扩展速率高于母材,基于简化的四参数全范围Forman模型可以表征主管道母材与焊材全范围的疲劳裂纹扩展规律。疲劳裂纹在奥氏体与铁素体相内主要呈穿晶扩展,但在部分区域裂纹沿?/?或?/?相界产生分支。A series of fatigue crack growth rate tests were carried out on the primary pipe of the pressurized water reactor nuclear power plant at room temperature, the research objects include base material and its TIG welded joint specimens. The fatigue crack growth rate was measured, and the crack propagation path was observed using an optical microscope.Furthermore, the sample fracture morphology was analyzed with a scanning electron microscope. The crack-growth curve identify that the crack growth rate of TIG welded joint specimen is higher than the base material. It is found that the Forman model can be used to describe the crack growth behavior for two materials. The crack predominantly shows a transgranular mode, but branch crack along the α/α or α/γ phase boundary was observed in the crack growth area.

关 键 词：国产压水堆核电站 主管道 自动焊 裂纹扩展 

分 类 号：TG146[一般工业技术—材料科学与工程]