Effect of surface quality on hydrogen/helium irradiation behavior in tungsten

被引:48
|
作者
Chen, Hongyu [1 ,2 ]
Xu, Qiu [3 ]
Wang, Jiahuan [1 ]
Li, Peng [1 ]
Yuan, Julong [1 ,2 ]
Lyu, Binghai [1 ,2 ]
Wang, Jinhu [1 ,2 ]
Tokunaga, Kazutoshi [4 ]
Yao, Gang [5 ,6 ]
Luo, Laima [5 ,6 ]
Wu, Yucheng [5 ,6 ]
机构
[1] Zhejiang Univ Technol, Coll Mech Engn, Hangzhou 310023, Peoples R China
[2] Zhejiang Univ Technol, Key Lab Special Purpose Equipment & Adv Proc Tech, Minist Educ & Zhejiang Prov, Hangzhou 310023, Peoples R China
[3] Kyoto Univ, Inst Integrated Radiat & Nucl Sci, Osaka, Japan
[4] Kyushu Univ, Res Inst Appl Mech, Kasuga, Fukuoka 8168580, Japan
[5] Hefei Univ Technol, Sch Mat Sci & Engn, Hefei 230009, Peoples R China
[6] Hefei Univ Technol, Natl Local Joint Engn Res Ctr Nonferrous Met & Pr, Hefei 230009, Peoples R China
基金
中国国家自然科学基金;
关键词
Tungsten; Surface quality; D(2)(+)retention; He irradiation; Radiation resistance; LOW-ENERGY; ION IRRADIATION; FLUX HELIUM; PLASMA; MICROSTRUCTURE; RETENTION; ALLOYS;
D O I
10.1016/j.net.2021.12.006
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
As the plasma facing material in the nuclear fusion reactor, tungsten has to bear the irradiation impact of high energy particles. The surface quality of tungsten may affect its irradiation resistance, and even affect the service life of fusion reactor. In this paper, tungsten samples with different surface quality were polished by mechanical processing, subsequently conducted by D-2(+) implantation and thermal desorption. D-2(+) implantation was performed at room temperature (RT) with the irradiation dose of 1 x 10(21) D-2(+)/m(2) by 5 keV D-2(+) ions, and thermal desorption spectroscopy measurements were done from RT to 900 K. In addition, He irradiation was also performed by 50 eV He+ ions energy with the fluxes of 5.5 x 10(21) m(-2)s(-1) and 1.5 x 10(22) m(-2)s(-1), respectively. Results reveal that the hydrogen/helium irradiation behavior are both related to surface quality. Samples with high surface quality has superior D(2+)retention behavior with less D-2 retained after implantation. However, such samples are more likely to generate fuzzes on the surface after helium irradiation. Different morphologies (smooth, wavy, pyramids) after helium irradiation also demonstrates that the surface morphology is related to tungsten crystallographic orientation. (C) 2021 Korean Nuclear Society, Published by Elsevier Korea LLC.
引用
收藏
页码:1947 / 1953
页数:7
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