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Author: Publisher: ISBN: Category : Languages : en Pages : 27
Book Description
A variety of experiments have been performed on the TFTR tokamak utilizing ICFR heating. Of special interest has been the insight into plasma performance gained by utilizing a different heating scheme other than the usual NBI. Utilizing ICRF heating allows control over the power deposition profile independent of the plasma fueling profile. In addition, by varying the minority concentration the power split between ion and electron heating can be varied. Confinement has been examined in high recycling gas fueled discharges, low recycling supershot plasmas, and peaked density pellet fueled discharges. Global confinement is found not to be affected by the method or localization of plasma heating, but the calculated local diffusivities vary with the power deposition profile to yield similar local values. In addition, sawtooth stabilization observed with ICRF heating has been investigated and found to occur in qualitative agreement with theory. ICRF sawtooth stabilized discharges exhibit peaked temperature and density profiles and have a safety factor q which appears to fall well below unity on axis. 11 refs., 10 figs.
Author: Publisher: ISBN: Category : Languages : en Pages : 27
Book Description
A variety of experiments have been performed on the TFTR tokamak utilizing ICFR heating. Of special interest has been the insight into plasma performance gained by utilizing a different heating scheme other than the usual NBI. Utilizing ICRF heating allows control over the power deposition profile independent of the plasma fueling profile. In addition, by varying the minority concentration the power split between ion and electron heating can be varied. Confinement has been examined in high recycling gas fueled discharges, low recycling supershot plasmas, and peaked density pellet fueled discharges. Global confinement is found not to be affected by the method or localization of plasma heating, but the calculated local diffusivities vary with the power deposition profile to yield similar local values. In addition, sawtooth stabilization observed with ICRF heating has been investigated and found to occur in qualitative agreement with theory. ICRF sawtooth stabilized discharges exhibit peaked temperature and density profiles and have a safety factor q which appears to fall well below unity on axis. 11 refs., 10 figs.
Author: Publisher: ISBN: Category : Languages : en Pages : 4
Book Description
Over the past two years, ICRF heating experiments have been performed on TFTR in the hydrogen minority heating regime with power levels reaching 11.2 MW in helium-4 majority plasmas and 8.4 MW in deuterium majority plasmas. For these power levels, the minority hydrogen ions, which comprise typically less than 10% of the total electron density, evolve into la very energetic, anisotropic non-Maxwellian distribution. Indeed, the excess perpendicular stored energy in these plasmas associated with the energetic minority tail ions is often as high as 25% of the total stored energy, as inferred from magnetic measurements. Enhanced losses of 0.5 MeV protons consistent with the presence of an energetic hydrogen component have also been observed. In ICRF heating experiments on JET at comparable and higher power levels and with similar parameters, it has been suggested that finite banana width effects have a noticeable effect on the ICRF power deposition. In particular, models indicate that finite orbit width effects lead to a reduction in the total stored energy and of the tail energy in the center of the plasma, relative to that predicted by the zero banana width models. In this paper, detailed comparisons between the calculated ICRF power deposition profiles and experimentally measured quantities will be presented which indicate that significant deviations from the zero banana width models occur even for modest power levels (P{sub rf} (approximately) 6 MW) in the TFTR experiments.
Author: Publisher: ISBN: Category : Languages : en Pages : 8
Book 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 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 3He (n{sub 3He}/n{sub e} = 15% - 30%). By changing the 3He 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.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Initial ion cyclotron range of frequencies (ICRF) heating experiments on TFTR began in the summer of 1988. Although we were in the commissioning stage for much of the equipment, some plasma coupling measurements were made in the fall. This paper is focused on the results from the Bay L antenna. 3 refs., 3 figs., 1 tab.
Author: Publisher: ISBN: Category : Languages : en Pages : 5
Book Description
Direct electron damping of the fast wave is a prerequisite to a viable current drive scenario for future steady-state tokamaks. It is also an attractive heating altemative to the standard ion resonance heating methods for DT experiments on TFTR because it does not require the addition of non-reactive ion species and avoids minority ion tails during studies of alpha-particle effects. The absence of minority ions in direct electron heating (DEH) also allows the use of RF power modulation to determine power deposition profiles and to carry out modulation transport studies to characterize electron transport in supershot plasmas, as described in this paper.
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Author: J. H. Rogers
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