Plasma Physics and Controlled Fusion · 2009 · 22 citations · 7 references
Natural SciencesNuclear EngineeringPhysicsFusion EngineeringPlasma PhysicsSimulation-based DesignFusion PlasmasHigh-temperature PlasmasMagnetic Confinement FusionMagnetized PlasmaPlasma ConfinementPlasma SimulationCurrent DensityCurrent Density ProfilesCurrent Drive In TokamaksMagnetic Flux ConsumptionPlasma Current DriveTokamak ConfinementTokamak PhysicsTokamak Plasmas
Lower hybrid (LH) assisted plasma current ramp-up in ITER is demonstrated using a free-boundary full tokamak discharge simulator which combines the DINA-CH and CRONOS codes. LH applied from the initial phase of the plasma current ramp-up increases the safety margins in operating the superconducting poloidal field coils both by reducing resistive ohmic flux consumption and by providing non-inductively driven plasma current. Loss of vertical control associated with high plasma internal inductance is avoided by tailoring the plasma current density profiles. Effects of early LH application on the plasma shape evolution are identified by the free-boundary plasma simulation.
7
A lower hybrid current drive system for ITER
G. T. Hoang, A. Bécoulet, J. Jacquinot et al. · Nuclear Fusion · 2009 · 134 citations · Full text
Engineering, Electrical Engineering, Nuclear Engineering +16
Simulations of steady-state scenarios for Tore Supra using the CRONOS code
Vladimir A. Basiuk, J. F. Artaud, F. Imbeaux et al. · Nuclear Fusion · 2003 · 123 citations
Simulation of the hybrid and steady state advanced operating modes in ITER
C. Kessel, G. Giruzzi, A. C. C. Sips et al. · Nuclear Fusion · 2007 · 99 citations