An experimental study of rod bundle dispersed-flow film boiling with high-pressure water
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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Related Subjects
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACCURACY
BOILING
CORRELATIONS
DISPERSIONS
ENERGY TRANSFER
FILM BOILING
FLUID MECHANICS
FORECASTING
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
FUEL-COOLANT INTERACTIONS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
MECHANICS
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
PWR TYPE REACTORS
REACTORS
ROD BUNDLES
SPACERS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS