Failure analysis of 316 stainless steel corrosion fatigue test fixture
作者
单位
1CAS Key Laboratory of Nuclear Materials and Safety Assessment、Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials、Institute of Metal Research、Chinese Academy of Sciences、Shenyang 110016、PR China 2School of Materials Science and Engineering、University of Science and Technology of China、Hefei 230026、PR China
关键词
收录来源
International Corrosion Congress · 第22届国际腐蚀大会
摘要
316 stainless steel was widely used in nuclear power and chemical industry due to its good corrosion re sistance, mechanical properties and high -temperature performance. In pressurized water reactor nuclear power plants, stainless steel was commonly used as the pipeline and reactor internals[1, 2]. The engineering de sign models usually based on the experimental data, and the stable service of fixtures is an important guarantee for the reliability of experimental data. The corrosion fatigue failure behavior of 316 stainless steel fixture used in high -temperature pressurized water environment was analyzed. It was found that the stress concentration at the right-angle transition position of the fixture was obvious which promoted the corrosion damage during fatigue test in high -temperature pressurized water. I nclusions were also observed at the crack initiation and propagation areas. The interaction between mechanical damage and environmental damage during fixture service was discussed and a rounded corner transition was proposed and analyzed for retarding stress concentration at transition position of the fatigue fixture.