Heat transfer above the two-phase mixture level under core uncovery conditions in a 336-rod bundle: data evaluation and analysis. Final report. [PWR]

Technical Report · Tue Dec 01 04:00:00 EST 1981

OSTI ID:5714414

Yeh, H C; Chiou, J S; Young, M Y

The heat transfer data obtained above the froth level of a 336-rod bundle in core uncovery tests were analyzed and several heat transfer correlations assessed in order to recommend an appropriate heat transfer model for use in small-break loss-of-coolant accident analyses. Existing heat transfer correlations were compared using two methods: (1) comparison of the predicted heat transfer coefficient with data and (2) comparison of the measured rod temperature with the temperatures calculated by using various other correlations. These comparisons showed that the most appropriate model is a modified form of the correlation derived from the FLECHT SEASET steam cooling tests for rod bundles and the Yao correlation for spacer grid effects.

• Research Organization: Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear Energy Systems Div.
• OSTI ID: 5714414
• Report Number(s): EPRI-NP-2161; ON: DE82901323
• Country of Publication: United States
• Language: English

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