Latest liquid lithium target design during the key element technology phase in the international fusion materials irradiation facility (IFMIF)-Reference-Cited by-同舟云学术

Latest liquid lithium target design during the key element technology phase in the international fusion materials irradiation facility (IFMIF)

Published:2003-09 Issue: Volume:66-68 Page:193-198
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Nakamura Hiroo,Riccardi B.,Ara K.,Burgazzi L.,Cevolani S.,Dell'Orco G.,Fazio C.,Giusti D.,Horiike H.,Ida M.,Ise H.,Kakui H.,Loginov N.,Matsui H.,Muroga T.,Nakamura Hideo,Shimizu K.,Takeuchi H.,Tanaka S.

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference13 articles.

1. A. Möslang, U. Fischer, V. Heinzel, P. Vladimirov, R. Ferdinand, H. Klein, et al., Proc. 19th Fusion Energy Conference, France, October 2002, IAEA-CN-94/FT1-2.

2. IFMIF-CDA Team, M. Martone (Ed.), IFMIF Conceptual Design Activity, Final Report, ENEA Frascati Report, RT/ERG/FUS/96/17, 1996.

3. IFMIF Team, A. Moeslang (Ed.), IFMIF Conceptual Design Evaluation Report, Forschungszentrum Karlsruhe report, FZKA 6199, January 1999.

4. H. Takeuchi, M. Sugimoto, H. Nakamura, T. Yutani, M. Ida, S. Jitsukawa, T. Kando, et al., Proceedings of the 18th Fusion Energy Conference, Italy, October 2000, IAEA-CN-77/FTP2/03.

5. Annual Report of NIFS Collaboration on Key Element Technology Development for Fusion Materials Irradiation Test facility, January 2001, National Institute for Fusion Science, in Japanese.

Cited by 8 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Development of remote handling technology of liquid lithium target and replaceable back plate with lip seal in IFMIF-EVEDA;Fusion Engineering and Design;2009-06

2. Radiation effects in IFMIF Li target diagnostic systems;Journal of Nuclear Materials;2009-04

3. Latest design of liquid lithium target in IFMIF;Fusion Engineering and Design;2008-12

4. Design of a lip seal-replaceable backwall for IFMIF liquid lithium target;Fusion Engineering and Design;2007-10

5. Non-inductive plasma operation scenario in tokamaks—possibilities for realization;Plasma Devices and Operations;2007-09