A method for determining poloidal coil configurations for tokamak devices
This paper presents a method for obtaining the locations and currents of the poloidal coil systems for a tokamak, given an desirable magnetohydrodynamic equilibrium for the device. The method involves a simultaneous minimization of the match to the desired poloidal field and the stored energy in the coils, subject to the constraints necessary to achieve decoupling of the equilibrium and inductive-current-drive (ohmic-heating) systems and to achieve a given coupling of the current-drive system with the plasma. A compendium of mutual and self-inductance formulas as they apply to tokamak systems is presented, as well as examples of how the method has been used in the design of several tokamaks. Finally, a user manual for a computer code that implements this method is provided. 14 refs., 11 figs., 1 tab.
- Research Organization:
- Argonne National Lab., IL (USA). Fusion Power Program
- Sponsoring Organization:
- DOE/ER
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6242831
- Report Number(s):
- ANL/FPP/TM-156; ON: DE91007940; TRN: 91-004502
- Country of Publication:
- United States
- Language:
- English
Similar Records
Starfire poloidal coil systems
Numerical study for determining PF coil system parameters in MHD equilibrium of KT-2 tokamak plasma
Related Subjects
TOKAMAK DEVICES
MAGNETIC FIELD CONFIGURATIONS
COMPUTER ARCHITECTURE
FERROMAGNETIC MATERIALS
JOULE HEATING
MHD EQUILIBRIUM
POLOIDAL FIELD DIVERTORS
CLOSED PLASMA DEVICES
DIVERTORS
ELECTRIC HEATING
EQUILIBRIUM
HEATING
MAGNETIC MATERIALS
MATERIALS
PLASMA HEATING
RESISTANCE HEATING
THERMONUCLEAR DEVICES
700202* - Fusion Power Plant Technology- Magnet Coils & Fields