ICRF heating and transport of deuterium-tritium plasmas in TFTR

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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. Confinement in an rf-heated supershot is at least similar to that without rf, and possibly ... continued below

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8 p.

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Murakami, M.; Batchelor, D.B. & Bush, C.E. December 31, 1994.

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Description

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. 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 {sup 3}He}/n{sub e} > 10%). 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 showed 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. Heat wave propagation showed no strong inward thermal pinch in off-axis heating of an ohmically-heated (OH) target plasma in TFIR.

Physical Description

8 p.

Notes

INIS; OSTI as DE95017443

Source

  • 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

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  • Other: DE95017443
  • Report No.: CONF-941182--5
  • Grant Number: AC05-84OR21400;AC02-76CH03073
  • DOI: 10.2172/113956 | External Link
  • Office of Scientific & Technical Information Report Number: 113956
  • Archival Resource Key: ark:/67531/metadc618424

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  • December 31, 1994

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

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  • May 2, 2016, 4:20 p.m.

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Murakami, M.; Batchelor, D.B. & Bush, C.E. ICRF heating and transport of deuterium-tritium plasmas in TFTR, report, December 31, 1994; Tennessee. (digital.library.unt.edu/ark:/67531/metadc618424/: accessed October 19, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.