IEEE Transactions on Applied Superconductivity · 2014 · 14 citations · 4 references
EngineeringElectrical EngineeringNuclear EngineeringFusion EngineeringPlasma PhysicsPower ElectronicsCurrent DrivePlasma ConfinementPlasma StabilityPower System DesignSuperconducting Magnet SystemsTokamak EngineeringActive ControlControl Systems For TokamaksFeasibility Study DesignMagnetic Coil DesignResponse TimeTokamak DesignTokamak PhysicsTokamak Plasmas
ITER plasma requires the use of an internal vertical stabilization (VS) coil set as part of the system for active control of vertical position. The required peak current and voltage of VS power supply are of order of 60 kA and 2.4 kV. Also, it needs short voltage response time, less than 1 ms and highly transient power demand. This paper describes a conceptual design study for the in-vessel vertical stabilization coil power supply system to judge design feasibility and estimate its cost. Finally, the result will be used as design input data for the ITER Tokamak building and other interface systems.
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Design of the ITER In-Vessel Coils
C. Neumeyer, A. Brooks, L.T. Bryant et al. · Fusion Science & Technology · 2011 · 37 citations · Full text
Engineering, Electrical Engineering, Nuclear Engineering +17