Key points are not available for this paper at this time.
The conceptual design of TORUS II SUPRA concerns a large sized Tokamak of the next generation. It takes into account constraints coming from the envisaged superconducting toroïdal magnet, but keeps unchanged all the operational facilities and working conditions which a more conventional design, i.e. a water cooled-copper magnet, could offer. The main parameters are R 0 = 2.15 m, a = 0.75 m, B 0 = 4.5 T, I = 1.7 MA. The scientific aims of the device concern the development, at a multimegawatt level, of plasma heating methods, mainly wave absorption and the contribution to high temperature (3-5 keV) Tokamak physics allowed by these methods : main emphasis is put on tentative profile control of plasma parameters during the quasi-steady state possible with a D.C. toroïdal magnetic field.
Aymar et al. (Mon,) studied this question.