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Plasma-facing material
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1	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. Add to Reading List Source URL: www.afs.enea.it Language: English - Date: 2011-03-09 05:25:41 Fusion power Tokamaks ASDEX Upgrade Neutral beam injection Divertor Plasma-facing material ITER Plasma KSTAR Experimental Advanced Superconducting Tokamak
2	A/Prof. Matthew Hole, Chair, Australian ITER Forum, Ph : +Fax: +http://www.ainse.edu.au/fusion The Secretariat, Add to Reading List Source URL: fusion.ainse.edu.au Language: English - Date: 2015-08-02 19:03:13 Nuclear technology Fusion power Energy conversion Nuclear chemistry Tokamaks ITER DEMO Nuclear power Laser Inertial Fusion Energy Plasma-facing material Fuel Nuclear reactor
3	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), Add to Reading List Source URL: www.afs.enea.it Language: English - Date: 2008-10-21 07:39:25 Fusion power Tokamaks Plasma physics ASDEX Upgrade High-confinement mode Plasma-facing material Max Planck Institute of Plasma Physics Plasma Magnetohydrodynamics Frascati Tokamak Upgrade Plasma stability
4	Lithium research as a plasma facing component material at the University of Illinois Add to Reading List Source URL: cpmi.illinois.edu Language: English - Date: 2015-04-22 08:46:32
5	Issues and Paths to Magnetic Confinement Fusion Energy Hutch Neilson Princeton Plasma Physics Laboratory Symposium on Worldwide Progress Toward Fusion Energy Add to Reading List Source URL: www.iter.org Language: English Fusion power Tokamaks ITER Princeton Plasma Physics Laboratory Magnetic confinement fusion DEMO Plasma Culham Centre for Fusion Energy Plasma-facing material
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 Add to Reading List Source URL: www.nifs.ac.jp - Date: 2013-12-18 20:53:38
7	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 Add to Reading List Source URL: www.nifs.ac.jp - Date: 2013-09-30 21:37:22

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