A nonequilibrium three-region model for transient analysis of pressurized water reactor pressurizer
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:5150007
A nonequilibrium three-region model is developed for the accurate prediction of the pressure in the pressurizer under both transient and accident conditions. The mathematical model derived from the general conservation equations includes all of the important thermal-hydraulics processes occurring in the pressurizer: bulk flashing and condensation, wall condensation, and interfacial heat and mass transfer, etc. The Stanton number for the interfacial heat transfer coefficient is obtained by fitting the experimental results in terms of the surge rate. The bubble rising and rain-out models are developed to describe bulk flashing and condensation, respectively. To obtain the wall condensation rate, a one-dimensional heat conduction equation is solved by the pivoting method. The mathematical model is numerically solved by the back substitution and successive iteration method for fast convergence and stability.
- Research Organization:
- Korea Advanced Institute of Science and Technology, Dept. of Nuclear Engineering, P.O. Box 150, Chongryang, Seoul
- OSTI ID:
- 5150007
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 74:3; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
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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
BENCH-SCALE EXPERIMENTS
BUBBLE GROWTH
DATA COVARIANCES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EQUATIONS
EVAPORATION
FLASHING
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
ITERATIVE METHODS
LOSS OF COOLANT
MASS TRANSFER
MATHEMATICAL MODELS
MECHANICS
NUMERICAL SOLUTION
PHASE TRANSFORMATIONS
POWER REACTORS
PRESSURIZERS
PRESSURIZING
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
SENSITIVITY ANALYSIS
SHIPPINGPORT REACTOR
STABILITY
SURGES
THERMAL CONDUCTION
THERMAL REACTORS
THERMODYNAMICS
THREE MILE ISLAND-2 REACTOR
TRANSIENTS
VAPOR CONDENSATION
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
BENCH-SCALE EXPERIMENTS
BUBBLE GROWTH
DATA COVARIANCES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EQUATIONS
EVAPORATION
FLASHING
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
ITERATIVE METHODS
LOSS OF COOLANT
MASS TRANSFER
MATHEMATICAL MODELS
MECHANICS
NUMERICAL SOLUTION
PHASE TRANSFORMATIONS
POWER REACTORS
PRESSURIZERS
PRESSURIZING
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
SENSITIVITY ANALYSIS
SHIPPINGPORT REACTOR
STABILITY
SURGES
THERMAL CONDUCTION
THERMAL REACTORS
THERMODYNAMICS
THREE MILE ISLAND-2 REACTOR
TRANSIENTS
VAPOR CONDENSATION
WATER COOLED REACTORS
WATER MODERATED REACTORS