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International Heat Transfer Conference 5

ISSN: 2377-424X (online)
ISSN: 2377-4371 (flashdrive)

A ROD-CENTERED SUBCHANNEL ANALYSIS WITH TURBULENT (ENTHALPY) MIXING FOR CRITICAL HEAT FLUX PREDICTION IN ROD CLUSTERS COOLED BY BOILING WATER

G.P. Gaspari
CISE - Segrate (Milan), Italy

A. Hassid
CISE - Segrate (Milan), Italy

F. Lucchini
CISE - Segrate (Milan), Italy

Abstract

An analysis is made of a recently suggested new concept - based on a "rod-centered" subchannel subdivision - for critical heat flux prediction in rod cluster geometry, to overcome some limitations as of interest for nuclear reactor safety assessment.
On the basis of an appropriate selection of data, an expression is derived to take into account entalphy exchange between subchannels. This expression, together with an accurate round tube correlation, appears to take into account satisfactorily most parameters affecting heat flux in the conditions interesting reactor safety.

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