中国电机工程学报Issue(8)：1310-1317,8.DOI:10.13334/j.0258-8013.pcsee.2014.08.014
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
摘要
Abstract
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/αorα/γphase 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Key words
China pressurized-water reactor/nuclear power plant/primary pipe/automatic welding/crack growth分类
矿业与冶金引用本文复制引用
薛飞,余伟炜,蒙新明,王兆希,刘伟,束国刚..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[J].中国电机工程学报,2014,(8):1310-1317,8.基金项目
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)。The Major State Basic Research Projects (973 Program)(2011CB 610506)；National Science and Technology Major Project(2011ZX 06004002)。 （973计划）
