DocumentCode
2071659
Title
Program CICC, flow and heat transfer in cable in conduit conductors
Author
Wong, Robert L.
Author_Institution
Lawrence Livermore Nat. Lab., California Univ., CA, USA
fYear
1989
fDate
2-6 Oct 1989
Firstpage
1134
Abstract
The computer program CICC has been written for use in the thermofluids 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 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
Keywords
fusion reactor theory and design; heat transfer; nuclear engineering computing; pipe flow; superconducting cables; CICC; background heating; cable-in-conduit conductors; computer program; conduit; epoxy-conduit insulation; flow; heat transfer; normal-zone propagation; pressure; superconducting magnets; superconductor cable; temperature; tokamak; Conductors; Electric resistance; Heat transfer; Inductors; Space heating; Superconducting cables; Superconducting magnets; Superconductivity; Temperature measurement; Tokamaks;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
Conference_Location
Knoxville, TN
Type
conf
DOI
10.1109/FUSION.1989.102411
Filename
102411
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