Plasma-facing material

Results: 7



#Item
11 FTP/2-4 Scenario Development for FAST in the View of ITER and DEMO F. Crisanti 1), R. Albanese 2), F. Artaud 3), O. Asunta 4), B. Baiocchi 5,6), M. Baruzzo 7), V.

1 FTP/2-4 Scenario Development for FAST in the View of ITER and DEMO F. Crisanti 1), R. Albanese 2), F. Artaud 3), O. Asunta 4), B. Baiocchi 5,6), M. Baruzzo 7), V.

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Source URL: www.afs.enea.it

Language: English - Date: 2011-03-09 05:25:41
2A/Prof. Matthew Hole, Chair, Australian ITER Forum, Ph : +Fax: +http://www.ainse.edu.au/fusion The Secretariat,

A/Prof. Matthew Hole, Chair, Australian ITER Forum, Ph : +Fax: +http://www.ainse.edu.au/fusion The Secretariat,

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Source URL: fusion.ainse.edu.au

Language: English - Date: 2015-08-02 19:03:13
31 EX/7-3Ra Disruption Control on FTU and ASDEX Upgrade with ECRH B. Esposito 1), G. Granucci 2), S. Nowak 2), J.R. Martin-Solis 3), L. Gabellieri 1),

1 EX/7-3Ra Disruption Control on FTU and ASDEX Upgrade with ECRH B. Esposito 1), G. Granucci 2), S. Nowak 2), J.R. Martin-Solis 3), L. Gabellieri 1),

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Source URL: www.afs.enea.it

Language: English - Date: 2008-10-21 07:39:25
4Lithium research as a plasma facing component material at the University of Illinois

Lithium research as a plasma facing component material at the University of Illinois

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Source URL: cpmi.illinois.edu

Language: English - Date: 2015-04-22 08:46:32
    5Issues and Paths to Magnetic Confinement Fusion Energy Hutch Neilson Princeton Plasma Physics Laboratory Symposium on Worldwide Progress Toward Fusion Energy

    Issues and Paths to Magnetic Confinement Fusion Energy Hutch Neilson Princeton Plasma Physics Laboratory Symposium on Worldwide Progress Toward Fusion Energy

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    Source URL: www.iter.org

    Language: English
    6§32. Induced W-rod Melting Experiment in the LHD Divertor Tanabe, T. (Kyushu Univ.), Masuzaki, S., Tokitani, M. Tungsten (W) is a candidate of plasma facing material (PFM) in the next generation fusion devices such as

    §32. Induced W-rod Melting Experiment in the LHD Divertor Tanabe, T. (Kyushu Univ.), Masuzaki, S., Tokitani, M. Tungsten (W) is a candidate of plasma facing material (PFM) in the next generation fusion devices such as

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    Source URL: www.nifs.ac.jp

    - Date: 2013-12-18 20:53:38
      7An estimation of retained hydrogen isotopes in plasma facing material and deposition layer are important issues in ITER and Demo reactors. Carbon-based materials (CBMs) are still one of the candidate and favorable for fu

      An estimation of retained hydrogen isotopes in plasma facing material and deposition layer are important issues in ITER and Demo reactors. Carbon-based materials (CBMs) are still one of the candidate and favorable for fu

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      Source URL: www.nifs.ac.jp

      - Date: 2013-09-30 21:37:22