Tritium distribution measurement of JET Mk IISRP divertor tiles

被引:9
|
作者
Tanabe, T.
Sugiyama, K.
Renvall, T.
Likonen, J.
Penttinen, L.
Vainonen-Ahlgren, E.
Coad, J. P.
机构
[1] Kyushu Univ, Interdisciplinary Grad Sch Engn Sci, Higashi Ku, Fukuoka 8128581, Japan
[2] VTT Proc, Assoc EURATOM TEKES, Espoo 02044, Finland
[3] Univ Helsinki, Lab Radiochem, FIN-00014 Helsinki, Finland
[4] UKAEA EURATOM, Fus Assoc, Culhum Sci Ctr, Abingdon OX14 3DB, Oxon, England
基金
日本学术振兴会;
关键词
tritium; JET; divertor; carbon-based materials; hydrogen retention;
D O I
10.1016/j.jnucmat.2007.01.191
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Tritium surface distribution on the JET Mark II Septum Replacement Plate (Mk II SRP) divertor tiles was measured by imaging plate technique. It was observed that areal tritium concentration was higher at the entrance of inner/outer pumping slots (so called 'shadowed area'). The tritium distribution profiles were similar to those obtained in the Mk IIA divertor which was exposed to a series of D-T plasma operation (DTE1). Tritium concentration of the plasma facing surface was lower compared to that of the shadowed area. Particularly, it was very low at the outer divertor surface. The inner divertor surface also showed low level of tritium retention, though it was covered by the thick carbon deposition on that. This could be caused by tritium release due to the temperature rise when the inner strike point was on the tiles. On the plasma shadowed area like tile gaps, high tritium retention owing to the codeposition was observed. (c) 2007 Elsevier B.V. All rights reserved.
引用
收藏
页码:960 / 965
页数:6
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