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International Heat Transfer Conference 7

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

REWET AND TRANSITION BOILING HEAT TRANSFER IN SIMULATED REACTOR FUEL BUNDLES

K. C. Chan
Nuclear Energy Division General Electric Company San Jose, California 95125 USA

F. S. Hong
Nuclear Energy Division General Electric Company San Jose, California 95125 USA

B. S. Shiralkar
General Electric Company, NED, San Jose, California

DOI: 10.1615/IHTC7.3470
pages 429-434

Abstract

The prediction of rewetting (or return to nucleate boiling) is one of the major uncertainties in using state-of-the-art computer codes to predict loss-of-coolant accident transients in nuclear reactors. Rewet and transition boiling heat transfer results were obtained from separate effects tests in a 4×4 simulated BWR fuel bundle and in a BWR system facility with one 8×8 simulated fuel bundle (Two-Loop Test Apparatus). Current rewet criteria using the concept of a minimum temperature are shown to be insufficient. Sufficient liquid must also be present for rewet to occur, which can be represented by a local quality criteria. This results in non-unique heat transfer characteristics on the boiling curve for the transition boiling regime.

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