Poloidal magnetics of compact ignition tokamaks
The present compact ignition tokamak (CIT) design point (R = 1.225 m, a = 0.454 m, B = 10.4 T, I = 10 MA) is optimized with respect to device size for limiter operation. The CIT poloidal field (PF) system is designed for both limiter and divertor (at I = 9 MA) scenarios. Forming a poloidal separatrix within the limiter vacuum chamber requires a divertor plasma elongation kappa = 2.0 and almost twice the PF energy as the limiter case. This study examines the dependence of PF system characteristics on the plasma elongation within the context of design points optimized for divertor operation. It is shown that higher elongation kappa = 2.0 considerably simplifies the CIT poloidal magnetic systems subject to device design constraints.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5796145
- Report Number(s):
- CONF-861110-4-Vugraphs; ON: DE88001774
- Country of Publication:
- United States
- Language:
- English
Similar Records
Poloidal magnetics and divertor strike point control in the Compact Ignition Tokamak
Poloidal magnetics of a divertor compact ignition tokamak
Related Subjects
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
CLOSED PLASMA DEVICES
COMPACT IGNITION TOKAMAK
DESIGN
DIVERTORS
LIMITERS
MAGNETIC FIELDS
MAGNETS
POLOIDAL FIELD DIVERTORS
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS