High Fusion Performance from Deuterium-tritium Plasmas in JET PDF Download
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Languages : en
Pages : 34
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Category :
Languages : en
Pages : 34
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Author: M. Keilhacker
Publisher:
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Category : Plasma (Ionized gases)
Languages : en
Pages :
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Languages : en
Pages :
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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][le] 2.5 MA) and high heating power (P[sub b][le] 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[minus] 1.5 MA. By peaking the plasma current profile, [beta][sub N dia][triple-bond] 10[sup 8][beta][sub t[perpendicular]] aB[sub 0]/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 : 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.
Author: K. M. McGuire
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Category : Controlled fusion
Languages : en
Pages : 17
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Author: K. M. McGuire
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Category : Controlled fusion
Languages : en
Pages : 17
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Author: S. A. Sabbagh
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Category :
Languages : en
Pages : 0
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Author:
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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: T. T. C. Jones
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Category :
Languages : en
Pages : 19
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Author: Y P Huo
Publisher: World Scientific
ISBN: 9814549665
Category :
Languages : en
Pages : 459
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The lectures given in the Summer School covered most of the important topics in controlled nuclear fusion and high temperature plasma physics. The topics are as follows: tokamak research, stellarator physics, transport and confinement of high temperature plasma, plasma-wall interaction and edge plasma physics, heating and current drive, diagnostics and general plasma theory.
