Tensile and low cycle fatigue behavior of primary pipe material for PWR nuclear power plant
A series of static tensile and low cycle fatigue tests for native PWR (Pressurized-water Reactor) primary pipe material were carried out under room temperature and elevated temperature of 350℃. In the monotonic tensile test,the tensile strength and elongation decreased as test temperature increased. The courses of uniform plastic deformation before necking at two temperatures could be divided into three stages. The Hollomon model parameters were obtained at different stages. In the strain-controlled fatigue test,it was found that the cyclic characteristics mainly depend on the test temperature and total strain amplitude. Following initial cyclic hardening for a few cycles,the material exhibited softening behavior,and the amount of initial hardening increased with increasing test temperature. Besides,the loading strain also played an important role during the process. The fatigue lives generally increased with an increase in testing temperature when the strain range was large. As the decreasing of strain amplitude,temperature effect impaired gradually,and they nearly got the same lives when the strain amplitude reached about 0.16％. Nevertheless,the transition life at elevated temperature was larger than that at room temperature.
Low cycle fatigue Nuclear power plant Primary pipe Elevated temperature
Fei Xue Guogang Shu Weiwei Yu Wenxin Ti Lei Lin Chongzhe Shi
China Guangdong Nuclear Power Suzhou Research Institute,Suzhou 240051,China Xian Technological University,Xian 710032,China
国际会议
Fracture Mechanics and Applications 2008(国际断裂力学2008年年会)(FM2008)
杭州
英文
293-298
2008-10-31（万方平台首次上网日期，不代表论文的发表时间）