DEUTERIUM-TRITIUM TFTR PLASMAS IN THE HIGH POLOIDAL BETA REGIME. PDF Download
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Author: S. A. Sabbagh
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Category :
Languages : en
Pages : 0
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Author: S. A. Sabbagh
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Author:
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Category :
Languages : en
Pages : 15
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Deuterium-tritium plasmas with enhanced energy confinement and stability have been produced in the high poloidal beta, advanced tokamak regime in TFTR. Confinement enhancement H {triple_bond} [tau]{sub E}/[tau]{sub E ITER-89P}> 4 has been obtained in a limiter H-mode configuration at moderate plasma current I{sub p} = 0.85 - 1.46 MA. By peaking the plasma current profile, [beta]{sub N dia} {triple_bond} 108 [beta]{sub t{perpendicular}} aB0/I{sub p} = 3 has been obtained in these plasma, s exceeding the [beta]{sub N} limit for TFTR plasmas with lower internal inductance, l{sub i}. Fusion power exceeding 6.7 MW with a fusion power gain Q{sub DT} = 0.22 has been produced with reduced alpha particle first orbit loss provided by the increased l{sub i}.
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Category :
Languages : en
Pages : 15
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Deuterium-tritium plasmas with enhanced energy confinement and stability have been produced in the high poloidal beta, advanced tokamak regime in TFTR. Confinement enhancement H {triple_bond} [tau]{sub E}/[tau]{sub E ITER-89P}> 4 has been obtained in a limiter H-mode configuration at moderate plasma current I{sub p} = 0.85 - 1.46 MA. By peaking the plasma current profile, [beta]{sub N dia} {triple_bond} 108 [beta]{sub t{perpendicular}} aB0/I{sub p} = 3 has been obtained in these plasma, s exceeding the [beta]{sub N} limit for TFTR plasmas with lower internal inductance, l{sub i}. Fusion power exceeding 6.7 MW with a fusion power gain Q{sub DT} = 0.22 has been produced with reduced alpha particle first orbit loss provided by the increased l{sub i}.
Author:
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Category :
Languages : en
Pages : 15
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Plasmas composed of nominally equal concentrations of deuterium and tritium (DT) have been created in TFTR with the goals of producing significant levels of fusion power and of examining the effects of DT fusion alpha particles. Conditioning of the limiter by the injection of lithium pellets has led to an approximate doubling of the energy confinement time, [tau]{sub E}, in supershot plasmas at high plasma current (I{sub p} d"2.5 MA) and high heating power (P{sub b} d"33 MW). Operation with DT typically results in an additional 20% increase in [tau]{sub E}. In the high poloidal beta, advanced tokamak regime in TFTR, confinement enhancement H {triple_bond} [tau]{sub E}/[tau]{sub E ITER-89P}> 4 has been obtained in a limiter H-mode configuration at moderate plasma current I{sub p} = 0.85 - 1.5 MA. By peaking the plasma current profile, [beta]{sub N dia} {triple_bond} 108 [beta]{sub t{perpendicular}} aB0/I{sub p} = 3 has been obtained in these plasmas, exceeding the [beta]{sub N} limit for TFTR plasmas with lower internal inductance, l{sub i}. Confinement of alpha particles appears to be classical and losses due to collective effects have not been observed. While small fluctuations in fusion product loss were observed during ELMs, no large loss was detected in DT plasmas.
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Category :
Languages : en
Pages : 55
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A new regime of high poloidal beta operation in TFTR was developed in the course of the first two years of this project (9/25/89 to 9/24/91). Our proposal to continue this successful collaboration between Columbia University and the Massachusetts Institute of Technology with the Princeton Plasma Physics Laboratory for a three year period (9/25/91 to 9/24/94) to continue to investigate improved confinement and tokamak performance in high poloidal beta plasmas in TFTR through the DT phase of operation was approved by the DOE and this is a report of our progress during the first 9 month budget period of the three year grant (9/25/91 to 6/24/92). During the approved three year project period we plan to (1) extend and apply the low current, high QDD discharges to the operation of TFTR using Deuterium and Tritium plasma; (2) continue the analysis and plan experiments on high poloidal beta phenomena in TFTR including: stability properties, enhanced global confinement, local transport, bootstrap current, and divertor formation; (3) plan and carry out experiments on TFTR which attempt to elevate the central q to values> 2 where entry to the second stability regime is predicted to occur; and (4) collaborate on high beta experiments using bean-shaped plasmas with a stabilizing conducting shell in PBX-M. In the seven month period covered by this report we have made progress in each of these four areas through the submission of 4 TFTR Experimental Proposals and the partial execution of 3 of these using a total of 4.5 run days during the August 1991 to February 1992 run.
Author: K. M. McGuire
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ISBN:
Category : Controlled fusion
Languages : en
Pages : 17
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Author: M. G. Bell
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Category : Tokamak Fusion Test Reactor (Project).
Languages : en
Pages : 10
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 15
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Plasmas composed of nominally equal concentrations of deuterium and tritium (DT) have been created in TFTR with the goals of producing significant levels of fusion power and of examining the effects of DT fusion alpha particles. Conditioning of the limiter by the injection of lithium pellets has led to an approximate doubling of the energy confinement time, [tau]{sub E}, in supershot plasmas at high plasma current (I{sub p} d"2.5 MA) and high heating power (P{sub b} d"33 MW). Operation with DT typically results in an additional 20% increase in [tau]{sub E}. In the high poloidal beta, advanced tokamak regime in TFTR, confinement enhancement H {triple_bond} [tau]{sub E}/[tau]{sub E ITER-89P}> 4 has been obtained in a limiter H-mode configuration at moderate plasma current I{sub p} = 0.85 - 1.5 MA. By peaking the plasma current profile, [beta]{sub N dia} {triple_bond} 108 [beta]{sub t{perpendicular}} aB0/I{sub p} = 3 has been obtained in these plasmas, exceeding the [beta]{sub N} limit for TFTR plasmas with lower internal inductance, l{sub i}. Confinement of alpha particles appears to be classical and losses due to collective effects have not been observed. While small fluctuations in fusion product loss were observed during ELMs, no large loss was detected in DT plasmas.
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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: K. M. McGuire
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 17
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