Interfacial transfer in annular dispersed flow. [PWR; BWR]
Conference
·
OSTI ID:6400704
The interfacial drag, droplet entrainment, droplet deposition and droplet-size distributions are important for detailed mechanistic modeling of annular dispersed two-phase flow. In view of this, recently developed correlations for these parameters are presented and discussed in this paper. The onset of droplet entrainment significantly alters the mechanisms of mass, momentum, and energy transfer between the film and gas core flow as well as the transfer between the two-phase mixture and the wall. By assuming the roll wave entrainment mechanism, the correlations for the amount of entrained droplet as well as for the droplet-size distribution have been obtained from a simple model in collaboration with a large number of data. Then the rate equations for entrainment and deposition have been developed. The drag correlations relevant to the droplet transfer is also presented. The comparison of the correlations to various data show satisfactory agreement.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6400704
- Report Number(s):
- CONF-820811-2; ON: DE83009571
- Country of Publication:
- United States
- Language:
- English
Similar Records
Hydrodynamics of annular-dispersed flow. [PWR; BWR]
Hydrodynamics of annular-dispersed flow
Hydrodynamics of annular-dispersed flow
Conference
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:6342488
Hydrodynamics of annular-dispersed flow
Conference
·
Thu Dec 31 23:00:00 EST 1981
· Am. Soc. Mech. Eng., Pressure Vessels Piping Div., (Tech. Rep.) PVP; (United States)
·
OSTI ID:6307694
Hydrodynamics of annular-dispersed flow
Conference
·
Thu Dec 31 23:00:00 EST 1981
· Am. Soc. Mech. Eng., Pressure Vessels Piping Div., (Tech. Rep.) PVP; (United States)
·
OSTI ID:5552061
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR PROTECTION SYSTEMS
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WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ANNULAR FUEL ELEMENTS
BWR TYPE REACTORS
DRAG
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
FLUID MECHANICS
FUEL ELEMENTS
HEAT TRANSFER
HYDRAULICS
MATHEMATICAL MODELS
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS