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

Abstract

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.

Authors:
 [1]
  1. Lawrence Livermore National Lab., CA (USA)
Publication Date:
Research Org.:
Lawrence Livermore National Lab., CA (USA)
Sponsoring Org.:
DOE/ER
OSTI Identifier:
5463489
Report Number(s):
UCRL-101241; CONF-891007-14
ON: DE90001519; TRN: 89-026119
DOE Contract Number:  
W-7405-ENG-48
Resource Type:
Conference
Resource Relation:
Conference: 13. international symposium on fusion engineering, Knoxville, TN (USA), 2-6 Oct 1989
Country of Publication:
United States
Language:
English
Subject:
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

Citation Formats

Wong, R L. Program CICC flow and heat transfer in cable-in-conduit conductors. United States: N. p., 1989. Web.
Wong, R L. Program CICC flow and heat transfer in cable-in-conduit conductors. United States.
Wong, R L. Mon . "Program CICC flow and heat transfer in cable-in-conduit conductors". United States. https://www.osti.gov/servlets/purl/5463489.
@article{osti_5463489,
title = {Program CICC flow and heat transfer in cable-in-conduit conductors},
author = {Wong, R L},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/5463489}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1989},
month = {11}
}

Conference:
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