Equilibrium field coil concepts for INTOR
Methods are presented for reducing ampere-turn requirements in the EF coil system. It is shown that coil currents in an EF coil system external to the toroidal field coils can be substantially reduced by relaxing the triangularity of a D-shaped plasma. Further reductions are realized through a hybrid EF coil system using both internal and external coils. Equilibrium field coils for a poloidally asymmetric, single-null INTOR configuration are presented. It is shown that the shape of field lines in the plasma scrapeoff region and divertor channel improves as triangularity is reduced, but it does so at the possible expense of achievable stable beta values.
- Research Organization:
- Oak Ridge National Lab., TN (USA); Grumman Aerospace Corp., Bethpage, NY (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6180996
- Report Number(s):
- ORNL/TM-7746; ON: DE81028032
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
BETA RATIO
CURRENTS
DESIGN
ELECTRIC COILS
ELECTRIC CURRENTS
ELECTRICAL EQUIPMENT
EQUIPMENT
INTOR TOKAMAK
MAGNET COILS
MAGNETIC FIELD CONFIGURATIONS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
BETA RATIO
CURRENTS
DESIGN
ELECTRIC COILS
ELECTRIC CURRENTS
ELECTRICAL EQUIPMENT
EQUIPMENT
INTOR TOKAMAK
MAGNET COILS
MAGNETIC FIELD CONFIGURATIONS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS