Computational investigation of fluid and thermal mixing of the EPRI/Creare onefifth-scale facility
During an overcooling transient in a pressurized water reactor, the cold water from the high-pressure safety system is injected into the hot primary coolant in the cold leg. This can cause the water temperature in the cold leg and downcomer annulus to decrease; hence, the problem of pressurized thermal shock arises. A multidimensional numerical study for the analysis of the Electric Power Research Institute/ Creare one-fifth-scale mixing test is performed. A new, accurate, stable mass-flow-weighted skew-upwind scheme is employed in the finite difference solution of the energy equation. The temperature predictions using the new scheme are in good agreement with the experimental data. A significant reduction in the numerical diffusion errors was achieved. These errors have plagued the conventional upwind scheme results. A good agreement between the computed velocity patterns and flow visualization is obtained.
- Research Organization:
- The Babcock and Wilcox Company, Lynchburg, Virginia
- OSTI ID:
- 5053554
- Journal Information:
- Nucl. Technol.; (United States), Vol. 68:3
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PRIMARY COOLANT CIRCUITS
THERMAL SHOCK
COMPUTERIZED SIMULATION
EPRI
FINITE DIFFERENCE METHOD
FLOW MODELS
FLOW VISUALIZATION
HEAT TRANSFER
HYDRAULICS
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR SAFETY
TRANSIENTS
TWO-PHASE FLOW
CONTAINERS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
ITERATIVE METHODS
MATHEMATICAL MODELS
MECHANICS
NUMERICAL SOLUTION
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
SIMULATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled