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Extensive experimental campaigns have been completed recently on both the JET and TFTR tokamaks. A substantial part of these programmes was devoted to assessing the physics and performance of ion cyclotron resonance heating (ICRH) scenarios in plasmas with up to 95% tritium fraction. The main emphasis was placed on schemes that are directly relevant to the ITER experimental reactor. This paper reviews the most important results with special emphasis on the implications for ITER. The TFTR experiments reported here were made mainly with combined ICRH and neutral beam injection (NBI) in circular supershot plasmas with high central ion temperatures. The JET results were obtained with ICRH alone in single-null, H-mode divertor plasmas with ITER-like shape and safety factor.

Additional information

Authors: START D F H, JET Joint Undertaking, Abingdon, Oxon (GB)
Bibliographic Reference: Report: JET-P(98)11 EN (1998) 16pp.
Availability: Available from the Publications Officer, JET Joint Undertaking, Abingdon, Oxon, OX14 3EA (GB)
Record Number: 199810823 / Last updated on: 1998-07-20
Original language: en
Available languages: en