Blister formation and deuterium retention on tungsten exposed to low energy and high flux deuterium plasma

被引:115
作者
Tokunaga, K
Baldwin, MJ
Doerner, RP
Noda, N
Kubota, Y
Yoshida, N
Sogabe, T
Kato, T
Schedler, B
机构
[1] Kyushu Univ, Appl Mech Res Inst, Kasuga, Fukuoka, Japan
[2] Univ Calif San Diego, Energy Res Ctr, La Jolla, CA 92093 USA
[3] Univ Calif San Diego, Dept Mech & Aerosp Engn, La Jolla, CA 92093 USA
[4] Natl Inst Fus Sci, Gifu 5095292, Japan
[5] Toyo Tanso Co LTD, Kagawa, Japan
[6] Nippon Plansee KK, Chiyoda Ku, Tokyo 1020083, Japan
[7] Plansee Aktiengesellschaft, A-6600 Reutte, Austria
关键词
bubbles & blister; deuterium inventory; high-z material; ion-surface interactions; tungsten coated carbon;
D O I
10.1016/j.jnucmat.2004.10.137
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Deuterium ion irradiation on tungsten has been carried out with incident energies of 100 eV and flux of 1 x 10(22) D+ m(-2) s(-1) at a temperature in range between 333 K and 1130 K up to a dose of 1 x 10(26) D+ m(-2). Three kinds of tungsten used are pure tungsten made by powder metallurgy tungsten (PM-W), vacuum plasma spray tungsten (VPS-W) and single crystal tungsten (SC-W). Surface morphology before and after the irradiation is observed with an SEM. In addition, retention property of deuterium after the irradiation is also examined with a TDS. Behavior of blister formation depends on the kind of the samples and the irradiation temperatures. TDS measurement also shows that deuterium is not retained in sample, which the blisters are not formed. The behavior of the blister formation and deuterium retention is influenced by the manufacturing process and the sample history of tungsten. (c) 2004 Elsevier B.V. All rights reserved.
引用
收藏
页码:887 / 891
页数:5
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