20th IEEE/NPSS Symposium onFusion Engineering, 2003. · 2006 · 11 citations · 1 references
Natural SciencesNuclear EngineeringPhysicsElectromagneticsFusion EngineeringPlasma PhysicsFusion PlasmasHigh-temperature PlasmasMagnetic Confinement FusionMagnetized PlasmaPlasma ConfinementSuperconducting Magnet SystemsCoil DesignMagnetic Coil DesignPoloidal Field Coil DesignPoloidal Magnetic FieldsSuperconducting Magnet DesignSuperconducting MagnetsTokamak DesignTokamak Plasmas
EAST(HT-7U) superconducting tokamak is an advanced steady-state plasma physics experimental device. The poloidal field (PF) coil system is used with superconducting conductor. The NbTi cable-in-conduit conduct (CICC) cooled by supercritical helium at 4.5 K is chosen as superconductor for all of the PF magnets. It was consisted of fourteen superconducting coils, located symmetrically about the equator plane of the machine. The PF system was supported by the case of TF coils. The final engineering design of PF system will be report in this paper. The maximum capacity of the volt seconds for EAST(experimental advanced superconducting tokamak) PF system is about 10 Web and the peak magnetic field in PF coils is about 4.5 T.
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Design of the Magnetic Field for HT-7U Tokamak
Weiyue Wu, Guo Zengji, Du Shijun · Plasma Science and Technology · 2000 · 15 citations