ION-CYCLOTRON RANGE OF FREQUENCIES HEATING AND FLOW GENERATION IN DEUTERIUM-TRITIUM PLASMAS

Recent radio-frequency heating experiments on the Tokamak Fusion Test Reactor (TFTR) [Hawryluk ct al., Plasma Phys. Controlled Fusion 33, 15 09 (1991)] have focused on developing tools for both pressure and curr ent profile control in deuterium-tritium (DT) plasmas. A new antenna w as added to investigate pressure profile control utilizing direct ion Bernstein wave (IBW) heating. This was the first time direct IBW heati ng was explored on TFTR. Plasma heating and driven poloidal hows are o bserved. Previously heating and current drive via mode-converted IBW w aves had been demonstrated in non-DT plasmas but efforts in DT plasmas had been unsuccessful. This lack of success had been ascribed to the presence of a small Li-7 minority ion population. In the most recent e xperiments Li-6 was used exclusively for machine conditioning and mode -conversion heating consistent with theory is now observed in DT plasm as. (C) 1998 American Institute of Physics.