Evolution of Dislocation Loops in AL-6XN Stainless Steels Irradiated by Hydrogen Ions  

作　　者：Zhong-Cheng Zheng Yan-Xia Yu Wei-Ping Zhang Zhen-Yu Shen Feng-Feng LUO Li-Ping Guo Yao-Yao Ren Rui Tang 

机构地区：[1]Hubei Nuclear Solid Physics Key Laboratory, Key Laboratory of Artificial Micro- and Nano-structures of Ministry of Education and School of Physics and Technology, Wuhan University, Wuhan 430072, China [2]Institute of Applied Physics, Jiangxi Academy of Science, -Nanchang 330029, China [3]Center for Electron Microscopy, Wuhan University, Wuhan 430072, China [4]Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu 610041, China

出　　处：《Acta Metallurgica Sinica(English Letters)》2017年第1期89-96,共8页金属学报（英文版）

基　　金：financial supports from the International Science and Technology Cooperation Program of China (No. 2015DFR60370);the National Natural Science Foundation of China (Nos. 11275140 and U1532134)

摘　　要：AL-6XN stainless steels, one of the candidate structure materials for supercritical water-cooled reactor, were irradiated from 0.5 to 5 dpa using 100 keV H2＋ ions at 290 and 380 ℃. Microstructures were characterized by transmission electron microscopy （TEM）. Dislocation loops were the dominant radiation-induced defects. All the dislocation loops had 1/3 〈111〉 type Burgers vector. Number density and size of the loops have been measured. Nucleation and evolution of dislocation loops were also investigated. Voids were observed only in the condition of 5 dpa at 380 ℃. Different evolution mechanisms of the radiation-induced dislocation loops were discussed. Effects of hydrogen and elevated temperature on the microstructural evolution were also investigated. Besides, the formed voids have a further effect on the evolution of dislocation loops.AL-6XN stainless steels, one of the candidate structure materials for supercritical water-cooled reactor, were irradiated from 0.5 to 5 dpa using 100 keV H2＋ ions at 290 and 380 ℃. Microstructures were characterized by transmission electron microscopy （TEM）. Dislocation loops were the dominant radiation-induced defects. All the dislocation loops had 1/3 〈111〉 type Burgers vector. Number density and size of the loops have been measured. Nucleation and evolution of dislocation loops were also investigated. Voids were observed only in the condition of 5 dpa at 380 ℃. Different evolution mechanisms of the radiation-induced dislocation loops were discussed. Effects of hydrogen and elevated temperature on the microstructural evolution were also investigated. Besides, the formed voids have a further effect on the evolution of dislocation loops.

关 键 词：Supercritical water-cooled reactor Austenitic stainless steels Ion irradiation Dislocation loops HYDROGEN 

分 类 号：TG142.71[一般工业技术—材料科学与工程]