Subcooled and low quality film boiling of water in vertical flow at atmospheric pressure. [PWR; BWR]
Technical Report
·
OSTI ID:5274332
Subcooled and low quality film boiling is usually encountered in safety analyses of nuclear reactors. In most of the previous subcooled film boiling studies, cryogenic fluids were used either in a stagnant pool or a forced convective set-up. These data cannot be applied to reactor safety analysis without excessive conservatism or skepticism. In this study, a unique method is used to establish flow film boiling of water in a vertical tube at atmospheric pressure. The data cover a mass flux range of 50 to 500 kg.m/sup -2/.s/sup -1/ and an inlet subcooling range of 5 to 70/sup 0/C. It is found that the heat transfer coefficient depends on the mass flux, inlet subcooling and the axial distance from the point where film boiling first starts. A physical model is developed to predict the wall temperature of a tube during inverted annular film boiling. It considers the thermal boundary layers in the subcooled liquid core and in the superheated vapor film. The predicted wall temperatures and void fractions compare well with the measurements.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5274332
- Report Number(s):
- NUREG/CR-2461; ANL-81-78; ON: DE82010533
- Country of Publication:
- United States
- Language:
- English
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Sun Jul 01 00:00:00 EDT 2012
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Sun Dec 31 23:00:00 EST 1989
· Experimental Heat Transfer; (USA)
·
OSTI ID:6529468
Related Subjects
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ACCIDENTS
BOILING
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ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
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FUEL CANS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PHASE TRANSFORMATIONS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
STRESSES
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS