Characteristics of Confinement and Fusion Reactivity in JT-60U High-[beta][rho] and TFTR Supershot Regimes with Deuterium Neutral Beam Injection PDF Download
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Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
The high performance regimes achieved in JT-60U and TFTR have produced peak DD fusion neutron rates up to 5.6[times] 10[sup 16]/s for similar heating beam powers, in spite of considerable differences in machine operation and plasma configuration. A common scaling for the DD fusion neutron rate (S[sub DD][proportional-to] P[sub abs][sup 2.0] H[sub ne] V[sub p][sup[minus]0.9]) is obtained, where P[sub abs] and H[sub ne] are the absorbed beam power and beam fueling peaking factor, respectively, and V[sub p] is the plasma volume. The maximum stored energy obtained in each machine has been up to 5.4 MJ in TFTR and 8.7 MJ in JT-60U. Further improvements in the fusion neutron rate and the stored energy are limited by the[beta]-limit in Troyon range, [beta][sub N][approximately] 2.0--2.5. A common scaling for the stored energy (W[sub tot][proportional-to] P[sub abs]V[sub p]H[sub ne][sup 0.2]) is also proposed.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
The high performance regimes achieved in JT-60U and TFTR have produced peak DD fusion neutron rates up to 5.6[times] 10[sup 16]/s for similar heating beam powers, in spite of considerable differences in machine operation and plasma configuration. A common scaling for the DD fusion neutron rate (S[sub DD][proportional-to] P[sub abs][sup 2.0] H[sub ne] V[sub p][sup[minus]0.9]) is obtained, where P[sub abs] and H[sub ne] are the absorbed beam power and beam fueling peaking factor, respectively, and V[sub p] is the plasma volume. The maximum stored energy obtained in each machine has been up to 5.4 MJ in TFTR and 8.7 MJ in JT-60U. Further improvements in the fusion neutron rate and the stored energy are limited by the[beta]-limit in Troyon range, [beta][sub N][approximately] 2.0--2.5. A common scaling for the stored energy (W[sub tot][proportional-to] P[sub abs]V[sub p]H[sub ne][sup 0.2]) is also proposed.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
TFTR has begun its campaign to study deuterium-tritium fusion under reactor-like conditions. Variable amounts of deuterium and tritium neutral beam power have been used to maximize fusion power, study alpha heating, investigate alpha particle confinement, and search for alpha driven plasma instabilities. Additional areas of study include energy and particle transport and confinement, ICRF heating schemes for DT plasmas, tritium retention, and fusion in high[beta][sub p] plasmas. The majority of this work is done in the TFTR supershot confinement regime. To obtain supershots, extensive limiter conditioning using helium fueled ohmic discharges and lithium pellet injection into ohmic and neutral beam heated plasmas is performed, resulting in a low recycling limiter. The relationship between recycling and core plasma confinement has been studied by using helium, deuterium and high-Z gas puffs to simulate high recycling limiter conditions. These studies show that confinement in TFTR supershots is very sensitive to the influx of neutral particles at the plasma edge.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
In TFTR plasmas at low to moderate density, the highest fusion energy gain Q/sub dd/ (D-D fusion power/injected power P/sub b/) is obtained with nearly balanced co- and counter-injection of neutral beams. For a given beam power, significantly unbalanced injection reduces Q/sub dd/ because the accompanying plasma rotation reduces the beam-target fusion reactivity, the fast-ion slowing-down time, and the beam-beam reaction rate, while and decrease from their maximum values. 9 refs., 3 figs., 1 tab.
Author: United States. Energy Research and Development Administration. Division of Magnetic Fusion Energy Publisher: ISBN: Category : Controlled fusion Languages : en Pages : 52
Author: Publisher: ISBN: Category : Languages : en Pages : 26
Book Description
TFTR experiments have emphasized the optimization of high performance plasmas as well as studies of transport in high temperature plasmas. The recent installation of carbon composite tiles on the main bumper limiter has allowed operation with up to 32 MW of neutral beam injection without degradation of plasma performance by large bursts of carbon impurities (carbon blooms''). Plasma parameters have been extended to T{sub i}(0) - 35 keV, T{sub e}(0) - 12 keV, n{sub e}(0) -1.2 × 102° m−3 producing D-D reaction rates of 8.8 × 1016 reactions per second. The fusion parameter n{sub e}(0)?{sub E}T{sub i}(0) in supershot plasmas is an increasing function of heating power up to an MHD stability limit, reaching values of -4.4 × 102° m−3 sec keV. Peaked-density-profile hot-ion plasmas with the edge characteristics of the H-mode have been produced in a circular cross-section limiter configuration with n{sub e}(0)?{sub E}T{sub i}(0) values characteristic of supershots, namely up to four times those projected for standard H-modes with broad density profiles. Reduced transport is also observed in the core of high-density ICRF-heated plasmas when the density profile is peaked. At the highest performance, the central plasma pressure in TFTR reaches reactor level values of 6.5 atmospheres. In these regimes, MHD instabilities with m/n = 1/1, 2/1, 3/2 and 4/3 are often observed concurrent with a degradation in performance. High?{sub p} plasmas with {var epsilon}?{sub p} ≈ 1.6 and?/(I/aB) ≈ 4.7 (%mT/MA) have demonstrated confinement enhancement over the low-mode confinement time with?{sub E}/?{sub L} - 3.5 and a bootstrap current of about 65% of the total plasma current.
Author: Publisher: ISBN: Category : Languages : en Pages : 15
Book Description
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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Author: Hyeon Keo Park
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Author: Weston M. Stacey
Author: United States. Energy Research and Development Administration. Division of Magnetic Fusion Energy
Author: Alan Coulter England
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