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Abstract

The Tore-Supra Tokamak permits, owing to the toroidal superconducting coils and the poloidal field system performances to realize long discharges, up to 30 seconds and more, for a nominal plasma current of 1,7 MA. Longer discharges are foreseen with a lower plasma current value. The poloidal field system consists of nine poloidal field coils, each one connected to its own power supply and all assembled in parallel to form a conductive shell. During the whole plasma discharge these coils are used to control the plasma current value and the plasma boundary position. A feed-back loop system elaborates the nine voltage references for the power supplies. A special design of this system is necessary due to the long pulse operation and the nine free parameters to control. The magnetic field measurements and the real-time computers will be described.

Additional information

Authors: BOTTEREAU J M, CEA, DEPARTEMENT DE RECHERCHES SUR LA FUSION CONTROLEE, SAINT-PAUL-LEZ-DURANCE (FRANCE);LE LUYER A, CEA, DEPARTEMENT DE RECHERCHES SUR LA FUSION CONTROLEE, SAINT-PAUL-LEZ-DURANCE (FRANCE);OUVRIER BUFFET P CEA, DEPARTEMENT DE RECHERCHES SUR LA FUSION CONTROLEE, SAINT-PAUL-LEZ-DURANCE (FRANCE), CEA, DEPARTEMENT DE RECHERCHES SUR LA FUSION CONTROLEE, SAINT-PAUL-LEZ-DURANCE (FRANCE)
Bibliographic Reference: 14TH SOFT CONFERENCE, AVIGNON (FRANCE), SEPT. 8-12, 1986 VOL. 1, PP. 693-698 1895 P., 1986, VOL. 1 AND VOL. 2, ISBN 0 08 034935 8 WRITE TO PERGAMON PRESS, HEADINGTON HILL HALL, OXFORD, OX3 0BW (UK), PRICE: UKL 220 (FOR BOTH VOLS.)
Record Number: 1989126043001 / Last updated on: 1989-01-01
Category: PUBLICATION
Available languages: en