Design of the PF system for EAST(HT-7U) tokamak

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...

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Bibliographic Details
Main Authors: Wu Weiyue, Li Baozeng, Zhuning
Format: Conference Proceeding
Language:English
Subjects:
Conductors
Niobium compounds
Physics
Plasma devices
Steady-state
Superconducting cables
Superconducting coils
Superconducting magnets
Titanium compounds
Tokamaks
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Summary: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.
DOI:10.1109/FUSION.2003.1426677