Review of deuterium–tritium results from the Tokamak Fusion Test Reactor
Thermonuclear Fusion
Fusion power
Limiter
DOI:
10.1063/1.871303
Publication Date:
2002-07-26T12:27:28Z
AUTHORS (200)
ABSTRACT
After many years of fusion research, the conditions needed for a D–T reactor have been approached on Tokamak Fusion Test Reactor (TFTR) [Fusion Technol. 21, 1324 (1992)]. For first time unique phenomena present in plasma are now being studied laboratory plasma. The magnetic experiments to study plasmas using nearly equal concentrations deuterium and tritium carried out TFTR. At maximum power 10.7 MW, 39.5 MW neutral-beam heating, supershot discharge 6.7 high-βp following current rampdown. density core is ≊2.8 m−3, exceeding that expected International Thermonuclear Experimental (ITER) [Plasma Physics Controlled Nuclear Research (International Atomic Energy Agency, Vienna, 1991), Vol. 3, p. 239] at 1500 total power. energy confinement time, τE, observed increase D–T, relative D plasmas, by 20% ni(0) Ti(0) τE product 55%. improvement thermal caused primarily decrease ion heat conductivity both limiter-H-mode discharges. Extensive lithium pellet injection increased 0.27 s enabled higher operation Ion cyclotron range frequencies (ICRF) heating plasma, second harmonic tritium, has demonstrated. First measurements confined alpha particles performed found be good agreement with TRANSP [Nucl. 34, 1247 (1994)] simulations. Initial ash profile compared simulations particle transport coefficients from He gas puffing experiments. loss detector bottom vessel well described first-orbit mechanism. No due alpha-particle-driven instabilities yet observed. TFTR will continue explore assumptions ITER design examine some physics issues associated an advanced tokamak reactor.
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