Plasma Science and Technology · 2000 · 15 citations · 2 references
EngineeringNuclear EngineeringPhysicsFusion EngineeringHeat TransferPlasma PhysicsMagnetic Confinement FusionMagnetized PlasmaNuclear FusionPlasma ConfinementSuperconducting Magnet SystemsTokamak EngineeringDesign CriteriaHeat Load CalculationSuperconducting Magnet DesignSuperconducting MagnetsSupport Structure DesignToroidal Field Coil DesignToroidal Field MagnetsWinding Design
HT-7U is a large fusion experimental device. It will be built in the Institute of Plasma Physics of Chinese Academy of Sciences. The mission of HT-7U is to develop the scientific basis for a continuously operating tokamak fusion reactor. This paper describes only a toroidal field (TF) superconducting magnet system of HT-7U. In this paper, design criteria of conductor and stability analysis, coil winding and support structure design of magnet system, mechanical calculation and stress analysis, heat load evaluation are given.
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TPX superconducting tokamak magnet system 1995 design and status overview
G.A. Deis, R.H. Bulmer, Richard D. Carpenter et al. · 2002 · 11 citations · Full text