IGNITEX experiment

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.<
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