Equilibrium modeling of the TFCX poloidal field coil system
The Toroidal Fusion Core Experiment (TFCX) isproposed to be an ignition device with a low safety factor (q approx. = 2.0), rf or rf-assisted startup, long inductive burn pulse (approx. 300 s), and an elongated plasma cross section (kappa = 1.6) with moderate triangularity (delta = 0.3). System trade studies have been carried out to assist in choosing an appropriate candidate for TFCX conceptual design. This report describes an important element in these system studies - the magnetohydrodynamic (MHD) equilibrium modeling of the TFCX poloidal field (PF) coil system and its impact on the choice of machine size. Reference design points for the all-super-conducting toroidal field (TF) coil (TFCX-S) and hybrid (TFCX-H) options are presented that satisfy given PF system criteria, including volt-second requirements during burn, mechanical configuration constraints, maximum field constraints at the superconducting PF coils, and plasma shape parameters. Poloidal coil current waveforms for the TFCX-S and TFCX-H reference designs consistent with the equilibrium requirements of the plasma startup, heating, and burn phases of a typical discharge scenario are calculated. Finally, a possible option for quasi-steady-state operation is discussed.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6894893
- Report Number(s):
- ORNL/FEDC-83/10; ON: DE84012040
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
DESIGN
ELECTRIC COILS
ELECTRICAL EQUIPMENT
ENERGY
EQUILIBRIUM
EQUIPMENT
FLUID MECHANICS
HYDRODYNAMICS
MAGNET COILS
MAGNETOHYDRODYNAMICS
MECHANICS
Q-VALUE
START-UP
THERMONUCLEAR IGNITION
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS