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Title: ICRF heating and transport of deuterium-tritium plasmas in TFTR

Abstract

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 themore » 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.« less

Authors:
; ; ; ; ; ; ; ; ;  [1]
  1. Princeton Plasma Physics Lab., NJ (United States); and others
Publication Date:
Research Org.:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
10115936
Report Number(s):
PPPL-3048
ON: DE95007362; TRN: 95:001634
DOE Contract Number:  
AC02-76CH03073
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Feb 1995
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; BERNSTEIN MODE; WAVE PROPAGATION; TFTR TOKAMAK; ICR HEATING; PULSED D-T REACTORS; CONFINEMENT TIME; MODE CONVERSION; 700350; 700310; 700340; PLASMA PRODUCTION, HEATING, CURRENT DRIVE, AND INTERACTIONS; PLASMA CONFINEMENT; PLASMA WAVES, OSCILLATIONS, AND INSTABILITIES

Citation Formats

Rogers, J H, Schilling, G, Stevens, J E, Taylor, G, Wilson, J R, Bell, M G, Budny, R V, Bretz, N L, Darrow, D, and Fredrickson, E. ICRF heating and transport of deuterium-tritium plasmas in TFTR. United States: N. p., 1995. Web. doi:10.2172/10115936.
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. ICRF heating and transport of deuterium-tritium plasmas in TFTR. United States. https://doi.org/10.2172/10115936
Rogers, J H, Schilling, G, Stevens, J E, Taylor, G, Wilson, J R, Bell, M G, Budny, R V, Bretz, N L, Darrow, D, and Fredrickson, E. 1995. "ICRF heating and transport of deuterium-tritium plasmas in TFTR". United States. https://doi.org/10.2172/10115936. https://www.osti.gov/servlets/purl/10115936.
@article{osti_10115936,
title = {ICRF heating and transport of deuterium-tritium plasmas in TFTR},
author = {Rogers, J H and Schilling, G and Stevens, J E and Taylor, G and Wilson, J R and Bell, M G and Budny, R V and Bretz, N L and Darrow, D and Fredrickson, E},
abstractNote = {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.},
doi = {10.2172/10115936},
url = {https://www.osti.gov/biblio/10115936}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Feb 01 00:00:00 EST 1995},
month = {Wed Feb 01 00:00:00 EST 1995}
}