Hydrogen isotope retention of JT-60U W-shaped divertor tiles exposed to DD discharges

被引:20
|
作者
Shibahara, T.
Tanabe, T.
Hirohata, Y.
Oya, Y.
Oyaidzu, M.
Yoshikawa, A.
Onishi, Y.
Arai, T.
Masaki, K.
Okuno, K.
Miya, N.
机构
[1] Kyushu Univ, Dept Adv Energy Engn Sci, Interdisciplinary Grad Sch Engn Sci, Higashi Ku, Fukuoka 8128581, Japan
[2] Hokkaido Univ, Grad Sch Engn, Sapporo, Hokkaido 0608628, Japan
[3] Nagoya Univ, Grad Sch Engn, Nagoya, Aichi 4648603, Japan
[4] Univ Tokyo, Radioisotope Ctr, Tokyo 1130032, Japan
[5] Shizuoka Univ, Grad Sch Engn, Shizuoka 4228529, Japan
[6] Japan Atom Energy Agcy, Fus Res & Dev Sector, Naka, Ibaraki 3110913, Japan
基金
日本学术振兴会;
关键词
D O I
10.1016/j.jnucmat.2006.06.001
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Deuterium (D) and Hydrogen (H) retention in carbon tiles exposed to DD and HH discharges in the JT-60U W-shaped divertor has been investigated by means of thermal desorption spectroscopy (TDS) and secondary ion mass spectrometry (SIMS). In the thick re-deposited layers on the outer divertor, hydrogen (H + D) was retained rather homogeneously with its concentration of 0.03 in (D + H)/C atomic ratio, which is attributed to the surface temperature rise above 900 K. Owing to the HH discharges performed after the DD discharges for tritium removal, H-dominated re-deposited layers were added on D-dominated re-deposited layers. In addition D retained in near surface layers were replaced by H both for re-deposited and eroded area. Accordingly deuterium concentration peaked at a little inside behind the H dominated surface layers for all tiles. The temperature increase during the discharge very likely causes the saturation of hydrogen retention even in the re-deposited layers. Accordingly the global wall saturation was observed in JT-60U. (c) 2006 Elsevier B.V. All rights reserved.
引用
收藏
页码:115 / 125
页数:11
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