3-3 Microstructure Evolution in EC316LN Austenitic Stainless Steel Irradiated in STIP-Ⅱ  

作　　者：Shen Tielong Wang Zhiguang Dai Yong 

机构地区：[1]不详 [2]Paul Scherrer Institut, 5232 Villigen PSI, Switzerland

出　　处：《IMP & HIRFL Annual Report》2014年第1期89-90,共2页中国科学院近代物理研究所和兰州重离子研究装置年报（英文版）

基　　金：National Natural Science Foundation of China(10835010, 91026002)

摘　　要：Austenitic stainless steels are a class structural material applied in current nuclear reactors and spallation targetsas well as future nuclear devices. It is well known, the migration and interaction of defects and their clusters andsmall dislocation loops caused by irradiation induce changes in mechanical properties of materials and result inradiation hardening and ductility loss of materials. In the present study, microstructure evolution in EC316LNaustenitic steel irradiated with mixed spectra of high-energy proton and spallation neutrons has been investigatedby using Transmission Electron Microscopy (TEM).

关 键 词：AUSTENITIC STAINLESS Steel 

分 类 号：O4[理学—物理]