Title of article :
Overview of fuel retention in composite and tungsten limiters
Author/Authors :
Rubel، نويسنده , , M. and Philipps، نويسنده , , V. and Pospieszczyk، نويسنده , , A. and Tanabe، نويسنده , , T. and Kِtterl، نويسنده , , S.، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2002
Pages :
5
From page :
111
To page :
115
Abstract :
A number of materials, in a form of limiters, have been tested at the TEXTOR tokamak as candidates for plasma facing components in future devices. The results for fuel distribution and content in sole tungsten and composites (vacuum plasma sprayed tungsten layer on graphite and a B4C coating on copper) are reported and compared with earlier obtained results for sole tungsten and graphite. In sole tungsten the deuterium content is below 1×1015 cm−2, whereas in case of the composite targets the inventory found in the hottest parts of the limiters is one at least order of magnitude greater. The fuel content on composites is predominantly related to the co-deposition process with carbon and boron. The influence of material damage (melting, detachment of a coating) and material mixing processes on the fuel retention is also addressed.
Journal title :
Journal of Nuclear Materials
Serial Year :
2002
Journal title :
Journal of Nuclear Materials
Record number :
1356057
Link To Document :
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