An experimental study of rod bundle dispersed-flow film boiling with high-pressure water

Journal Article · Mon Apr 01 04:00:00 EST 1985 · Nucl. Technol.; (United States)

OSTI ID:6413298

Morris, D G; Mullins, C B; Yoder, G L

Dispersed-flow film boiling data were obtained in a large rod bundle (8 X 8) under steady-state and transient conditions with upward flowing high-pressure, high-temperature water. The bundle is equipped with detailed thermometry, and has geometry typical of later generation pressurized water reactors with 17 X 17 fuel assemblies. Comparisons with the data to empirical correlations commonly used to predict heat transfer in dispersed flow indicate that the Dougall-Rohsenow and Groeneveld-Delorme correlations overpredict and underpredict heat transfer, respectively, while the Groeneveld 5.7 and Condie-Bengston IV correlations perform reasonably well. Spacer grids are shown to cause rod surface temperature depressions of up to 100 K from the upstream to downstream side of the grid. Grid effects persist for 20 to 30 hydraulic diameters downstream of the grid.

• Research Organization: Oak Ridge National Laboratory, Engineering Technology Division, Oak Ridge, Tennessee
• OSTI ID: 6413298
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 69:1; ISSN NUTYB
• Country of Publication: United States
• Language: English

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