Nonequilibrium flashing model for rapid pressure transients. [PWR]
Conference
·
OSTI ID:5462665
A detailed, microscopic model for the nonequilibrium flashing of water is coupled to equations describing the bulk liquid state in order to calculate rapid pressure response to an induced liquid strain. The flashing model is predicated on the dynamics of a single bubble growing in an infinite liquid, and it encompasses both the inertia and conduction-limited regimes of bubble growth. The analysis is valid at high temperatures. It is not limited by the assumption of a thin thermal boundary layer for the bubble or by a prescribed boundary layer shape. The analysis can predict arbitrary pressure transients, both decompressive and recompressive. The flashing model involves the solution of a system of ordinary and partial differential equations constituting a classic moving-boundary problem. The solution is obtained numerically by the method of lines and by the use of automatic software.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA); Babcock and Wilcox Co., Lynchburg, VA (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5462665
- Report Number(s):
- CONF-810804-24; ON: DE82007639
- Country of Publication:
- United States
- Language:
- English
Similar Records
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Journal Article
·
Tue Jan 31 23:00:00 EST 1984
· J. Heat Transfer; (United States)
·
OSTI ID:7021896
Nonequilibrium vapor-generation model for flashing flows
Conference
·
Wed Dec 31 23:00:00 EST 1980
·
OSTI ID:5341944
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Conference
·
Fri Jun 01 00:00:00 EDT 1979
·
OSTI ID:5943014
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
EVAPORATION
FLASHING
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDRODYNAMICS
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
PHASE TRANSFORMATIONS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
EVAPORATION
FLASHING
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDRODYNAMICS
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
PHASE TRANSFORMATIONS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS