ICRF Heating of Deuterium-tritium Plasmas in TFTR. PDF Download
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Author: H. G. Adler
Publisher:
ISBN:
Category : Tokamak Fusion Test Reactor (Project)
Languages : en
Pages : 13
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Book Description
Author: H. G. Adler
Publisher:
ISBN:
Category : Tokamak Fusion Test Reactor (Project)
Languages : en
Pages : 13
Get Book Here
Book Description
Author: H. G. Adler
Publisher:
ISBN:
Category : Tokamak Fusion Test Reactor (Project).
Languages : en
Pages : 13
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 8
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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 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: G. Taylor
Publisher:
ISBN:
Category :
Languages : en
Pages : 7
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Author: J. Hosea
Publisher:
ISBN:
Category :
Languages : en
Pages : 4
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Author: K. M. McGuire
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 17
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Author:
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ISBN:
Category :
Languages : en
Pages : 618
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Author:
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ISBN:
Category :
Languages : en
Pages : 19
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During the past two years, deuterium-tritium (D-T) plasmas in the Tokamak Fusion Test Reactor (TFTR) have been used to study fusion power production, isotope effects associated with tritium fueling, and alpha-particle physics in several operational regimes. The peak fusion power has been increased to 10.7 MW in the supershot mode through the use of increased plasma current and toroidal magnetic field and extensive lithium wall conditioning. The high-internal-inductance (high -li) regime in TFTR has been extended in plasma current and has achieved 8.7 MW of fusion power. Studies of the effects of tritium on confinement have now been carried out in ohmic, NBI- and ICRF-heated L-mode and reversed-shear plasmas. In general, there is an enhancement in confinement time in D-T plasmas which is most pronounced in supershot and high-li discharges, weaker in L-mode plasmas with NBI and ICRF heating and smaller still in ohmic plasmas. In reversed-shear discharges with sufficient deuterium-NBI heating power, internal transport barriers have been observed to form, leading to enhanced confinement. Large decreases in the ion heat conductivity and particle transport are inferred within the transport barrier. It appears that higher heating power is required to trigger the formation of a transport barrier with D-T NBI and the isotope effect on energy confinement is nearly absent in these enhanced reverse-shear plasmas. Many alpha-particle physics issues have been studied in the various operating regimes including confinement of the alpha particles, their redistribution by sawteeth, and their loss due to MHD instabilities with low toroidal mode numbers. In weak-shear plasmas, alpha-particle destabilization of a toroidal Alfven eigenmode has been observed.
Author: C. E. Bush
Publisher:
ISBN:
Category : Tokamak Fusion Test Reactor (Project).
Languages : en
Pages : 16
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Author: K. M. McGuire
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 17
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