Title :
IGNITEX experiment
Author :
Carrera ; Barrington ; Bickerton ; Booth ; Chen, Yuanfeng ; Dong, Junchen ; Driga ; Eways ; Fu, G. ; Gully ; Hallock ; Helton ; Hertel ; Hively ; Howell, J. ; Hsieh, Kuang-Yeu ; Ling, Jonathan ; Miller, G. ; Montalvo ; Ordonez, Camilo ; Palmrose ; Parish
Author_Institution :
Texas Univ., Austin, TX, USA
Abstract :
Summary Form only given, as follows. The fusion ignition experiment IGNITEX is described. The experiment is to be realized in a compact (R=1.5 m), single-turn coil tokamak with a high magnetic field (20 T) and high plasma current (12 MA). The high level of magnetic field permits ohmic heating to ignition, high stability margin, and high plasma current with moderate elongation (K=1.6). The high plasma current improves the thermal energy balance to the plasma and relaxes its operational limits. A high ignition margin is possible in IGNITEX. Thermally stable plasmas can be produced during the ignited phase of the discharge.<>
Keywords :
fusion reactor ignition; fusion reactor operation; IGNITEX; discharge; fusion ignition experiment; high plasma current; high stability margin; ignited phase; ohmic heating; operational limits; single-turn coil tokamak; thermal energy balance; Fusion power generation;
Conference_Titel :
Plasma Science, 1989. IEEE Conference Record - Abstracts., 1989 IEEE International Conference on
Conference_Location :
Buffalo, NY, USA
DOI :
10.1109/PLASMA.1989.166018
