HIGH POWER ICRF HEATING ON THE DIVERTOR TOKAMAK ASDEX
First ICRF experiments on ASDEX have been performed at 67 MHz, corresponding to 2-CH-heating of a hydrogen plasma at B-o = 2.2T. Despite divertor operation ICRH is accompanied by a significant increase of impurity production which can be drastically be reduced by means of wall carbonization. RF power up to 2.3 MW is routinely coupled to the plasma for pulse lengths of up to 1 sec. The rf heating is found to depend strongly on plasma preheating. In combination with neutral injection the ICRF heating efficiency is even higher than the one of NI. NI-L-Confinement degrades with ICRH to values in between type and OH confinement.
Bibliographic Reference: 12TH EUROPEAN CONFERENCE ON CONTROLLED FUSION AND PLASMA PHYSICS, BUDAPEST (HUNGARY), SEPT. 2-6, 1985 WRITE TO MAX-PLANCK-INSTITUT FUER PLASMAPHYSIK, 8046 GARCHING BEI MUENCHEN (GERMANY), MENTIONING REPORT IPP III/107, 1985, PP. 65-68.
Record Number: 1989124096500 / Last updated on: 1987-01-01
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