Overview of fuel retention in composite and tungsten limiters

被引：24

作者：

Rubel, M

Philipps, V

Pospieszczyk, A

Tanabe, T

Kötterl, S

机构：

[1] Royal Inst Technol, Alfven Lab, EURATOM Assoc, VR, S-10044 Stockholm, Sweden

[2] Forschungszentrum Julich, EURATOM Assoc, Inst Plasma Phys,TEC, D-52425 Julich, Germany

[3] Nagoya Univ, Ctr Integrated Res Sci & Engn, Chikusa Ku, Nagoya, Aichi 464, Japan

[4] Max Planck Inst Plasma Phys, EURATOM Assoc, D-85748 Garching, Germany

来源：

JOURNAL OF NUCLEAR MATERIALS | 2002年 / 307卷

关键词：

D O I：

10.1016/S0022-3115(02)00940-6

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

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.

引用

页码：111 / 115

页数：5

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