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(ITERP/02) ITER-FEAT Magnetic Configuration and Plasma Position/Shape Control in the Nominal PF Scenario

Y. V. Gribov1), R. Albanese2), G. Ambrosino2), M. Ariola2), R. H. Bulmer3), M. Cavinato1), E. Coccorese2), H. Fujieda4), A. Kavin1), R. Khayrutdinov5), K. Lobanov6), V. Lukash7), L. Makarova6), A. Mineev6), P. L. Mondino1), A. Pironti2), A. Portone8), E. Rumyantsev6), I. Senda4), T. Shoji4), V. Vasiliev6)
1) ITER Joint Central Team, Naka Joint Work Site, Naka-machi, Ibaraki-ken, Japan
2) Association EURATOM/ENEA/CREATE, Reggio Calabria, Italy
3) LLNL, Livermore, California, USA
4) JAERI Naka Fusion Research Establishment, Naka-machi, Ibaraki-ken, Japan
5) TRINITI, Troitsk, Moscow Region, Russia
6) Efremov Institute, St. Petersburg, Russia
7) Kurchatov Institute, Moscow, Russia
8) EFDA, CSU, Max Planck Institute for Plasma Physics, Garching, Germany

Abstract.  The capability of the ITER-FEAT poloidal field system to support the four ``design'' scenarios and the high current ``assessed'' scenario have been studied. To operate with highly elongated plasma, the system has segmentation of the central solenoid and a separate fast feedback loop for plasma vertical stabilisation. Within the limits imposed on the coil currents, voltages and power, the poloidal field system provides the required plasma scenario and control capabilities. The separatrix deviation from the required position, in scenarios with minor disruptions is within less than about 100 mm.

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IAEA 2001