TECHNICAL FEATURES AND PROGRESS OF ASDEX UPGRADE
The objective of ASDEX Upgrade is to investigate open poloidal divertor configurations as produced by a reactor- compatible, poloidal field coil system. The accessible poloidal and toroidal fields and hence the plasma current provide a sufficiently large plasma parameter regime to ensure the functioning of the open divertor. The toroidal field magnet consists of 16 D-shaped coils encased by a rigid support structure of cast austenitic steel. The poloidal field system is comparable to the toroidal magnet with regard to the size and amount of conductor material and support structure. It consists of ohmic heating coils, multipole field coils and control coils for plasma position and shape. A steel framework supports the huge vertical forces. The vacuum vessel is all-metal as seen from the plasma side. The necessary toroidal resistance is provided by 8 steel bellows which bridge the insulated sector flanges. A water-cooled graphite structure was developed for the divertor target plate. It was tested up to a power flux density of 12 MW/m2 steady-state. Vertical plasma control and stability relies on the time scale provided by the response of a short-circuit saddle coil inside the vacuum vessel close to the plasma. The whole structure inside the vacuum vessel was adjusted to the single-null divertor configuration. The plasma is to be heated with a power of up to 15 MW, made up of 6 MW ion cyclotron heating and 6 to 9 MW neutral injection heating. The tokamak system components coils, support structures and vacuum vessel are now being manufactured. Special technical features of the design and fabrication methods are described.
Bibliographic Reference: 14TH SOFT CONFERENCE, AVIGNON (FRANCE), SEPT. 8-12, 1986 VOL. 1, PP. 161-172 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: 1989126046701 / Last updated on: 1989-01-01
Available languages: en