作者: Qiangmao WAN , Guogang SHU , Rongshan WANG , Hui DING , Xiao PENG
DOI: 10.3724/SP.J.1037.2012.00060
关键词: Reactor pressure vessel 、 Microstructure 、 Dislocation 、 Proton 、 Embrittlement 、 Irradiation 、 Copper 、 Materials science 、 Metallurgy 、 Grain boundary
摘要: Irradiation embrittlement of reactor pressure vessel (RPV) steels is one the critical issues for integrity and safety in long-life operation light water reactors. The em- brittlement attributed to three main nano-scale microstructural features including copper rich precipitates, matrix damage grain boundary segregation. relevance component can be high low content alloys also case doses. Some recent works have been done trying clarify exact nature this dam- age irradiated commercial steels. This still an open question: how irradiation-induced microstructure will evolve A508-3 steel dose range. In present work, order emulate neutron irradiation RPV steels, 190 keV proton irradiations were conducted on a 0.108, 0.216 0.271 dpa at room temperature. -induced was examined by TEM. obtained results show that induced defects are mainly dislocation loops, majority which both � 100� type interstitial type, without observation micro-voids. Dislocation loops distribute roughly evenly matrix, some decorate pre-existing lines.