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An auxiliary heating system suitable for Next Step devices such as ITER (International Thermonuclear Experimental Reactor) must be able to perform at least the following two main tasks: (i) heat the plasma to ignition; (ii) drive the plasma current non-inductively with a high efficiency. The latter appears to be an essential requirement for continuous operation of a tokamak reactor. The fast wave ion cyclotron resonance heating (ICRH) system is used for the above tasks, and demonstrates the plasma heating capabilities of this experiment. Further, theory predicts that the fast waves have a good potential for efficient non-inductive current drive in ITER. Although minority ion current drive for sawtooth control has been adequately demonstrated experimentally, the electron current drive by fast waves has seen a slow evolution in its demonstration principally because of the low electron temperature that exists in present day devices. Positive experimental results of the electron current drive are reported from the DIII-D tokamak and Tore Supra. To alleviate the problem of low electron temperature, this paper proposes to use a mode conversion electron heating scheme that has been optimised and adapted in TFTR to the antennas located on the low-field side of the present-day tokamaks.

Additional information

Authors: BHATNAGAR V P, JET Joint Undertaking, Abingdon, Oxon. (GB);JACQUINOT J, JET Joint Undertaking, Abingdon, Oxon. (GB);LASHMORE-DAVIES C, AEA Fusion, Culham Laboratory, Abingdon, Oxon. (GB)
Bibliographic Reference: Report: JET-R(94)12 EN (1994) 28 pp.
Availability: Available from the Publications Officer, JET Joint Undertaking, Abingdon, Oxon. OX14 3EA (GB)
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