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High power fast waves are routinely used in Tokamaks either in the ion cyclotron resonance heating (ICRH) regime or, by adjusting the frequency to avoid this powerful resonance, in the electron damping regime. Recently, JET has been modified to accommodate a new divertor, the Mark I, which is the first in a series of divertors being tested for ITER. This is the first stage of a programme of divertor optimization coupled with studies of high performance plasmas in ITER-like geometry. The purpose of this paper is to present the new features which have been observed in H-modes with ICRH in the Mark I divertor configuration on JET.

Additional information

Authors: GORMEZANO C ET AL, JET Joint Undertaking, Abingdon, Oxon (GB)
Bibliographic Reference: Report: JET-P(96)60 EN (1996) 27pp.
Availability: Available from the Publications Officer, JET Joint Undertaking, Abingdon, Oxon, OX14 3EA (GB)
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