High-performance TF coil design for the Toroidal Fusion Core Experiment (TFCX)

Conference · Sun Jan 01 00:00:00 EST 1984

OSTI ID:6401966

Srivastava, V C

The Toroidal Fusion Core Experiment (TFCX) is a proposed concept for an ignited, long-pulse, current-driven tokamak device. TF coil winding cross section in the inboard region is impacted by peak field 10 T, winding current density approx. 3500 A/cm/sup 2/, and peak nuclear heating rates 50 mW/cc. 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 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 an Nb/sub 3/Sn conductor is strongly dependent on strain in the superconducting strands. The strain in strands is lower when the windings are: (a) wound and then reacted (W/R), as compared to (b) 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 LHe inlet (approx. 4/sup 0/K) and outlet (approx. 5.5/sup 0/K) connections are located on the sides of the TF coils. The conductor design, the winding design, and performance analysis are described.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6401966
• Report Number(s): CONF-840937-7; ON: DE85001127
• Resource Relation: Conference: Applied superconductivity conference, San Diego, CA, USA, 9 Sep 1984
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
71 CLASSICAL AND QUANTUM MECHANICS
GENERAL PHYSICS
SUPERCONDUCTING MAGNETS
DESIGN
TFCX REACTORS
NIOBIUM ALLOYS
PERFORMANCE
SPECIFICATIONS
STRAINS
TIN ALLOYS
ALLOYS
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
MAGNETS
SUPERCONDUCTING DEVICES
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
700202* - Fusion Power Plant Technology- Magnet Coils & Fields
420201 - Engineering- Cryogenic Equipment & Devices