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Fusion power / Tokamaks / ASDEX Upgrade / Neutral beam injection / Divertor / Plasma-facing material / ITER / Plasma / KSTAR / Experimental Advanced Superconducting Tokamak
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

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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