High-performance TF coil design for the Tokamak Fusion Core Experiment (TFCX)
The Tokamak Fusion Core Experiment (TFCX) is a proposed concept for an ignited, long-pulse, currentdriven tokamak device. Toroidal field (TF) coil winding cross section in the inboard region is impacted by peak field (10 T), winding current density (about 3500 A/cm/sup 2/), and peak nuclear heating rates (50 mW/cm/sup 3/). The winding utilizes a Nb/sub 3/Sn internally cooled cable superconductor (ICCS), which is a modified version of the conductor used in the Westinghouse Large Coil Program (LCP) coil. These modifications include the increase of void fraction from 32% to 41% of the cable space for withstanding higher nuclear heating rates and a thicker conduit wall to carry larger magnetic loads. The critical current of a Nb/sub 3/Sn conductor is strongly dependent on strain in the superconducting strands. The strain in strands is lower when the windings are wound and then reacted (W/R), as compared to reacted and then wound (R/W). The impact of these approaches on winding performance is discussed. The windings are pancake wound and cooled with supercritical helium. The liquid helium (LHe) inlet (about 4 K) and outlet (about 5.5 K) connections are located on the sides of the TF coils. The conductor design, the winding design, and performance analysis are described.
- Research Organization:
- Fusion Engineering Design Center/General Electric Company, Oak Ridge National Laboratory, Oak Ridge, Tennessee
- OSTI ID:
- 6331764
- Report Number(s):
- CONF-840937-
- Journal Information:
- IEEE Trans. Magn.; (United States), Vol. MAG 21:2; Conference: Applied superconductivity conference, San Diego, CA, USA, 9 Sep 1984
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
SUPERCONDUCTING MAGNETS
DESIGN
PERFORMANCE TESTING
TFCX REACTORS
CRITICAL FIELD
CRYOGENIC FLUIDS
CURRENT DENSITY
HELIUM
LABORATORIES
LARGE COIL PROGRAM
NIOBIUM ALLOYS
STRAINS
SUPERCONDUCTING CABLES
THERMONUCLEAR REACTOR COOLING SYSTEMS
TIN ALLOYS
ALLOYS
CABLES
CONDUCTOR DEVICES
COOLING SYSTEMS
ELECTRIC CABLES
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
ELEMENTS
ENERGY SYSTEMS
EQUIPMENT
FLUIDS
GASES
MAGNETIC FIELDS
MAGNETS
NONMETALS
RARE GASES
SUPERCONDUCTING DEVICES
TESTING
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
700209* - Fusion Power Plant Technology- Component Development & Materials Testing
700202 - Fusion Power Plant Technology- Magnet Coils & Fields