Plasma material interaction studies on low activation materials used for plasma facing or blanket component-Reference-Cited by-同舟云学术

Plasma material interaction studies on low activation materials used for plasma facing or blanket component

Published:2004-08 Issue: Volume:329-333 Page:673-677
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Hino T,Hirohata Y,Yamauchi Y,Hashiba M,Kohyama A,Katoh Y,Lee Y,Jinushi T,Akiba M,Nakamura K,Yoshida H,Sengoku S,Tsuzuki K,Kusama Y,Yamaguchi K,Muroga T

Publisher

Elsevier BV

Subject

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

Reference9 articles.

1. IAEA, Technical basis for ITER-FEAT outline design, ITER EDA Documentation Series No. 19, IAEA, Vienna, 2000

2. Tritium inventory of carbon dust in ITER

3. Deuterium retention of co-deposited carbon dust

4. T. Hino, Y. Hirohata, Y. Yamauchi, S. Sengoku, in: Proceedings of 18th IAEA Fusion Energy Conference, IAEA-CN-77/FTP1/08, IAEA, 2000

5. A. Kohyama, Y. Katoh, S.M. Dong, T. Hino, in: Proceedings of 19th IAEA Fusion Energy Conference, IAEA-CN-77/FT/P1-02, IAEA, 2002

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