Poloidal field coil and current distribution study for the Toroidal Fusion Core Experiment (TFCX). Draft
The Toroidal Fusion Core Experiment (TFCX) is a proposed concept for an ignited, long-pulse, current-driven, ''next step'' tokamak device. The poloidal field (PF) coil configuration has major impact on the size and cost of a tokamak machine. The purpose of this trade study was to determine the achievable values of plasma triangularity and elongation consistent with mechanical configuration and plasma performance requirements. The study was made with three sets of PF coil configurations: (1) PF coils external to the (TF) coil, (2) all PF coils inside the TF coil bore, and (3) a hybrid configuration with some coils inside and some outside of the TF coil bore. The impact of plasma shape, profile, and coil locations on the distance between the plasma boundary and separatrix are presented. It is concluded that the plasma scrape-off requirements for removing impurities with a single null limiter can only be satisfied if the triangularity is limited to approx. 0.30 for an elongation of 1.6.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5710095
- Report Number(s):
- CONF-831203-194; ON: DE85012345
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
700200* -- Fusion Energy-- Fusion Power Plant Technology
CURRENTS
DESIGN
ELECTRIC COILS
ELECTRIC CURRENTS
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
MAGNET COILS
MAGNETS
SPECIFICATIONS
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
TFCX REACTORS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS