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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 x 10(15) 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. (C) 2002 Elsevier Science B.V. All rights reserved.
