Comparison of analytic and lumped-parameter solutions for steady-state heat transfer in fuel-rod assemblies

Conference · Mon Jan 01 04:00:00 EST 1973

OSTI ID:4398105

Ginsberg, T; France, D M; Dwyer, O E ^[1]

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1. ed.

From 4th international seminar on heat and mass transfer in liquid metals; Trojir, Yugoslavia (6 Sep 1971). See CONFA comparative study of analytic and lumped-parameter methods applied to steady-state heat transfer in nuclear fuel-rod assemblies is presented. The two methods were applied to an idealized, finite fuel-rod system which displays essential features of real fuel assemblies. Results of this investigation show that excellent agreement between the two methods can be obtained if theoretically predicted length scales are used as effective mixing lengths'' for conduction heat transfer in the COBRA-II lumped-parameter computer code. If, however, adjacent cellular (sub-channel) centroidto-centroid distances arc used to approximate the effective mix ing lengths,'' significant errors are generated in the temperature distributions predictcd by lumped-parameter methods. Evidence is presented which indicates that these errors in the lumpedparameter solution can be reduced by subdividing the fuel assembly into a larger number of cells. (auth)

• Research Organization: Argonne National Lab., IL
• NSA Number: NSA-29-000285
• OSTI ID: 4398105
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

*FUEL ELEMENT CLUSTERS-- HEAT TRANSFER
*LIQUID METAL COOLED REACTORS- - FUEL ELEMENT CLUSTERS
*LIQUID METALS-- HEAT TRANSFER
ANALYTICAL SOLUTION
C CODES
FLOW RATE
FUEL RODS
LIQUID FLOW
N42300* --Engineering--Heat Transfer & Fluid Flow
NUMERICAL SOLUTION