ICRF heating and transport of deuterium-tritium plasmas in TFTR

Technical Report · Wed Feb 01 04:00:00 EST 1995

DOI:https://doi.org/10.2172/10115936· OSTI ID:10115936

Rogers, J H; Schilling, G; Stevens, J E; Taylor, G; Wilson, J R; Bell, M G; Budny, R V; Bretz, N L; Darrow, D; Fredrickson, E ^[1]

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1. Princeton Plasma Physics Lab., NJ (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 beating 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 3He}/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. Analysis of heat wave propagation showed no strong inward thermal pinch in off-axis heating of an ohmically-heated target plasma in TFTR.

• Research Organization: Princeton Univ., NJ (United States). Plasma Physics Lab.
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC02-76CH03073
• OSTI ID: 10115936
• Report Number(s): PPPL--3048; ON: DE95007362
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700310
700340
700350
BERNSTEIN MODE
CONFINEMENT TIME
ICR HEATING
MODE CONVERSION
PLASMA CONFINEMENT
PLASMA PRODUCTION, HEATING, CURRENT DRIVE, AND INTERACTIONS
PLASMA WAVES, OSCILLATIONS, AND INSTABILITIES
PULSED D-T REACTORS
TFTR TOKAMAK
WAVE PROPAGATION