Microstructural evolution in W-1%TiC alloy irradiated He ions at high temperatures  

作　　者：Q.Xu H.Y.Chen L.M.Luo M.Miyamoto M.Tokitani Y.C.Wu 

机构地区：[1]Institute for Integrated Radiation and Nuclear Science,Kyoto University,Osaka 590-0494,Japan [2]Ultra-Precision Machining Center,Zhejiang University of Technology,Hangzhou 310014,China [3]School of Materials Science and Engineering,Hefei University of Technology,Hefei 230031,China [4]Shimane University,Matsue 690-8504,Shimane,Japan [5]National Institute for Fusion Science,Gifu 509-5292,Japan

出　　处：《Tungsten》2019年第3期229-235,共7页钨科技（英文）

基　　金：the auspices of the NIFS Collaboration Research Program(Grant No.NIFS17KLPF055).

摘　　要：To investigate the surface damage of a material by He ions,a dispersion-strengthened W-1wt%TiC alloy was irradiated by 5-keV He ions at 773 K,973 K,and 1173 K up to an ion dose of 1.8×10^(21)He m−2,respectively.No He bubble formation was observed under transmission electron microscopy at any temperature for He doses less than 1.5×10^(20)He m^(−2).When this dose was exceeded,He bubbles grew and void swelling increased with increasing irradiation doses.Naturally,the growth of He bubbles and the void swelling became more pronounced with increasing irradiation temperatures.Compared to the published data on commercially available pure W,the formation of He bubbles was suppressed by TiC particles in the W-TiC alloy,especially at low doses.

关 键 词：W-TiC He irradiation He bubble 

分 类 号：TG1[金属学及工艺—金属学]