Microstructure,hardening and deuterium retention in CVD tungsten irradiated with neutrons at temperatures of defect recovery stagesⅡandⅢ  

作　　者：Xiao-Ou Yi Tatsuya Kuwabara Vladimir KhAlimov Yu-Feng Du Wen-Tuo Han Ping-Ping Liu Bin-You Yan Jiu-Peng Song Kenta Yoshida Takeshi Toyama Fa-Rong Wan Somei Ohnuki Yuji Hatano Yasuyoshi Nagai 

机构地区：[1]School of Materials Science and Engineering,University of Science and Technology Beijing,Beijing,100083,China [2]Graduate School of Engineering,Nagoya University,Furo-cho,Chikusa-ku,Nagoya,464-8063,Japan [3]Frumkin Institute of Physical Chemistry and Electrochemistry,Russian Academy of Sciences,Moscow,119071,Russia [4]Institute for Materials Research,Tohoku University,Narita-cho 2145-2,Oarai,Ibaraki,311-1313,Japan [5]Xiamen Tungsten Co.Ltd.,Xiamen,361021,China [6]School of Materials Science and Engineering,Xihua University,Chengdu,610039,China [7]Hydrogen Isotope Research Center,University of Toyama,Toyama,930-8555,Japan

出　　处：《Tungsten》2022年第3期248-260,共13页钨科技（英文）

基　　金：Neutron irradiations at BR2 in SCK/CEN were carried out in the framework of MICADO project.Hot-lab experiments were conducted at the International Research Centre for Nuclear Materials Science(Oarai site),Institute for Materials Research(IMR),Tohoku University.All authors wish to thank IMR staffs Mr.K.Suzuki and T.Maniwa for their kind assistance.X.Yi acknowledges funding support from the Global Institute for Materials Research Tohoku(GIMRT)program via proposals No.19M0504,20M0502 and 202012-IRKMA-0516;the National Natural Science Foundation of China via grant No.12175013;J.P.Song acknowledges funding support from the National Magnetic Confinement Fusion Program of China via Grant No.2018YFE031210.

摘　　要：Samples of ultra-high-purity tungsten prepared using chemical vapour deposition(CVD)technique were irradiated with neutrons at temperatures T_(irr)=373-483 K(stage Ⅱ of defect recovery)and T_(irr)=573-673 K(stage Ⅲ)up to 0.15 displacements per atom(dpa)in the Belgian reactor(BR2).The study of the microstructure of neutron-damaged samples using transmission electron microscopy(TEM)revealed visible defects with a predominance of dislocation loops.With an increase in the neutron irradiation temperature,the spatial distribution of the loops acquired pronounced inhomogeneity,and their average size moderately increased.Cavities and voids were not observed.Irradiation-induced hardening was found and a linear correlation was obtained between Vickers microhardness and nanohardness for undamaged and neutron-irradiated CVD-W samples.Irradiation of tungsten with neutrons led to a significant increase in the retention of deuterium,which accumulated mainly in vacancy-type traps.Furthermore,the influence of the columnar grain structure in low-dose neutron-irradiated tungsten seemed to be non-trivial upon deuterium retention.

关 键 词：CVD-W Neutron irradiation MICROSTRUCTURE HARDENING Deuterium retention 

分 类 号：TG146.411[一般工业技术—材料科学与工程]