Tritium decontamination from co-deposited layer on tungsten substrate by ultra violet lamp and laser

被引:6
作者
Oya, Y [1 ]
Tadokoro, T [1 ]
Shu, W [1 ]
Hayashi, T [1 ]
O'Hira, S [1 ]
Nishi, M [1 ]
机构
[1] Japan Atom Energy Res Inst, Dept Fus Engn Res, Tritium Engn Lab, Naka, Ibaraki 3191195, Japan
关键词
tritium decontamination; ultraviolet radiation; co-deposited layer; nuclear fusion; lazer radiation; irradiation; radiation effects;
D O I
10.3327/jnst.38.967
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
Tritium decontamination using ultra violet (UV) lamp and laser was performed. Simulated co-deposited layer on tungsten substrate was deposited by C2H2 or C2D2 glow discharge. The co-deposited layer was irradiated to UV lights from a xenon excimer lamp (172 nm) or ArF excimer laser (193 nm) and the in-situ decontamination behavior was evaluated by a mass spectrometer. After the UV irradiation, the hydrogen concentration in the co-deposited layer was evaluated by elastic recoil detection analysis (ERDA) and the depth profile was analyzed by secondary ion mass spectrometry (SIMS). For the co-deposited layer formed by C2D2 glow discharge, it was found that M/e 3 (HD) gas was released mainly during the UV lamp irradiation while both M/e 3 (HD) and M/e 4 (D-2) gases were detected during the UV laser irradiation. Though the co-deposited layer was not removed by UV lamp irradiation, almost all the co-deposited layer was removed by UV laser irradiation within 1 min. The ratio of hydrogen against carbon in the co-deposited layer was estimated to be 0.53 by ERDA and the number of photon needed for removing 1 mum thick co-deposited layer was calculated to be 3.7 x 10(18) cm(-2) for the UV laser by SIMS measurement. It is concluded that C-H (C-D) bond on the co-deposited layer were dissociated by irradiation of UV lamp while the co-deposited layer itself was removed by the UV laser irradiation.
引用
收藏
页码:967 / 970
页数:4
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