IEEE Transactions on Magnetics · 1979 · 45 citations · 2 references
EngineeringNuclear EngineeringPhysicsFusion EngineeringHeat TransferPlasma PhysicsMagnetic Confinement FusionNuclear FusionPlasma ConfinementSuperconducting Magnet SystemsTokamak EngineeringInductive Plasma HeatingPlasma Heating SystemsSuperconducting Magnet DesignSuperconducting MagnetsTokamak DesignTokamak PhysicsTokamak PlasmasToroidal Field Magnets
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 <inf xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">0</inf> = 2.15 m, a = 0.75 m, B <inf xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">0</inf> = 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.
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