Deuterium--tritium high confinement (H-mode) studies in the Tokamak Fusion Test Reactor
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- Princeton University, Plasma Physics Laboratory, P.O. 451, Princeton, New Jersey 08543 (United States)
High or enhanced confinement (H-mode) plasmas have been obtained for the first time with nearly equal concentrations of deuterium and tritium in high-temperature, high poloidal beta plasmas in the Tokamak Fusion Test Reactor (TFTR) [McGuire, Phys. Plasmas {bold 2}, 2176 (1995)]. Tritium fueling was provided mainly through high-power neutral beam injection (NBI) with powers up to 31 MW and beam energies of 90--110 keV. A transition to a circular limiter H-mode configuration has been obtained, following a programmed rapid decrease of the plasma current. Isotope effects, due to the presence of tritium, led to different behavior for deuterium--deuterium (DD) and deuterium--tritium (DT) H-modes relative to confinement, edge localized magnetohydrodynamic modes (ELMs), and ELM effects on fusion products. However, the threshold power for the H-mode transition was the same in DD and DT. Some of the highest values of the global energy confinement time, {tau}{sub {ital E}}, have been achieved on TFTR during the ELM-free phase of DT H-mode plasmas. Enhancements of {tau}{sub {ital E}} greater than four times the L-mode have been attained.
- OSTI ID:
- 55923
- Journal Information:
- Physics of Plasmas, Journal Name: Physics of Plasmas Journal Issue: 6 Vol. 2; ISSN PHPAEN; ISSN 1070-664X
- Country of Publication:
- United States
- Language:
- English
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