Program CICC flow and heat transfer in cable-in-conduit conductors

Conference · Mon Nov 20 00:00:00 EST 1989

OSTI ID:5463489

Wong, R L ^[1]

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1. Lawrence Livermore National Lab., CA (USA)

Computer program CICC has been written for use in the thermo-fluids design of superconducting magnets for tokamak reactors, which use forced-flow, helium-cooled, cable-in-conduit conductors (CICC). In addition to background heat loads that vary with space and time, these superconductors can develop normal zones that generate electrical resistance heat. Program CICC models the transient thermodynamic and fluid-dynamic system response to background heating and normal-zone propagation in the superconductor. The computational algorithm described in this paper couples a one-dimensional, compressible pipe-flow model (including flow choking) with two-dimensional, axisymmetric heat-conduction models of the superconductor cable, the conduit, and the epoxy-conduit insulation. National Institute of Standards and Technology helium properties are used. The model is verified by comparison with measured temperature and pressure profiles from thermal expulsion experiments. 10 refs., 9 figs.

• Research Organization: Lawrence Livermore National Lab., CA (USA)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 5463489
• Report Number(s): UCRL-101241; CONF-891007-14; ON: DE90001519; TRN: 89-026119
• Resource Relation: Conference: 13. international symposium on fusion engineering, Knoxville, TN (USA), 2-6 Oct 1989
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
SUPERCONDUCTING CABLES
HEAT TRANSFER
C CODES
DESIGN
SUPERCONDUCTING MAGNETS
TOKAMAK DEVICES
CABLES
CLOSED PLASMA DEVICES
COMPUTER CODES
CONDUCTOR DEVICES
ELECTRIC CABLES
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
ENERGY TRANSFER
EQUIPMENT
MAGNETS
SUPERCONDUCTING DEVICES
THERMONUCLEAR DEVICES
700202* - Fusion Power Plant Technology- Magnet Coils & Fields