Westinghouse best-estimate LOCA analysis model: WCOBRA/TRAC
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:7118611
A rule change for 10CFR50.46 and Appendix K has been proposed by the US Nuclear Regulatory Commission (NRC). This change would allow the use of realistic (best-estimate) thermal-hydraulic computer codes to predict the emergency core cooling system performance for a postulated large-break loss-of-coolant accident (LOCA). The NRC staff expects that the analytical techniques used for predicting the design-basis large-break LOCA, will use realistic thermal-hydraulic models and will be based on applicable experimental data. WCOBRA/TRAC is a three-dimensional separated flow code that models the two-phase flow with three component fields: vapor phase, continuous liquid phase, and entrained liquid. The formulation of the governing equations is complete and includes turbulence models for the continuous phase. There is one continuity equation for each field, three momentum equations for each field (total of 9), and two energy equations. WCOBRA/TRAC meets the requirements for a realistic thermal-hydraulic model, which can be used to accurately predict postulated accident transients for a pressurized water reactor.
- OSTI ID:
- 7118611
- Report Number(s):
- CONF-8711195-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 55
- 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
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
C CODES
COMPUTER CODES
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
NATIONAL ORGANIZATIONS
PERFORMANCE
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
T CODES
TWO-PHASE FLOW
US NRC
US ORGANIZATIONS
W CODES
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
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
C CODES
COMPUTER CODES
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
NATIONAL ORGANIZATIONS
PERFORMANCE
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
T CODES
TWO-PHASE FLOW
US NRC
US ORGANIZATIONS
W CODES
WATER COOLED REACTORS
WATER MODERATED REACTORS