ICRF heating and transport of deuterium-tritium plasmas in TFTR
- Oak Ridge National Lab., TN (United States); and others
This paper describes results of the first experiments utilizing high-power ion cyclotron range of frequency (ICRF) to heat deuterium-tritium (D-T) plasmas in reactor-relevant regimes on the Tokamak Fusion Test Reactor (TFTR). Results from these experiments have demonstrated efficient core, second harmonic, tritium heating of D-T supershot plasmas with tritium concentrations ranging from 6%-40%. Significant direct ion heating on the order of 60% of the input radio frequency (rf) power has been observed. The measured deposition profiles are in good agreement with two-dimensional modeling code predictions. Energy confinement in an rf-heated supershot is at least similar to that without rf, and possibly better in the electron channel. Efficient electron heating via mode conversion of fast waves to ion Bernstein waves (IBW) has been demonstrated in ohmic, deuterium-deuterium and DT-neutral beam injection plasmas with high concentrations of minority {sup 3}He(n{sub 3(He)}/n{sub e}=15%-30%). By changing the {sup 3}He concentration or the toroidal field strength, the location of the mode-conversion radius was varied. The power deposition profile measured with rf power modulation indicated that up to 70% of the power can be deposited on electrons at an off-axis position. Preliminary results with up to 4 MW coupled into the plasma by 90-degree phased antennas showed directional propagation of the mode-converted IBW. 20 refs., 6 figs.
- DOE Contract Number:
- AC02-76CH03073; AC05-84OR21400
- OSTI ID:
- 219748
- Report Number(s):
- CONF-941182-; ISSN 0748-1896; TRN: 96:010825
- Journal Information:
- Fusion Technology, Vol. 27; Conference: 6. international Toki conference on plasma physics and controlled nuclear fusion: Research for advanced concepts in magnetic fusion, Toki-city (Japan), 29 Nov - 2 Dec 1994; Other Information: PBD: Apr 1995
- Country of Publication:
- United States
- Language:
- English
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ICRF heating and transport of deuterium-tritium plasmas in TFTR
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