High heat flux testing of plasma facing materials and components – Status and perspectives for ITER related activities-Reference-Cited by-同舟云学术

High heat flux testing of plasma facing materials and components – Status and perspectives for ITER related activities

Published:2007-08 Issue: Volume:367-370 Page:1422-1431
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Linke J.,Escourbiac F.,Mazul I.V.,Nygren R.,Rödig M.,Schlosser J.,Suzuki S.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference21 articles.

1. M. Merola, J. Palmer, in: Proc. Intern. Symposium on Fusion Nuclear Technology, Tokyo, 22–27 May, 2005.

2. Manufacture of blanket shield modules for ITER

3. ITER divertor, design issues and research and development

4. Materials for the plasma-facing components of fusion reactors

5. J. Linke, P. Lorenzetto, P. Majerus, M. Merola, D. Pitzer, M. Rödig, in: Proc. ANS 16th Topical Meeting on the Technology of Fusion Energy, Madison, Wisconsin, 14–16 September, 2004.

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