Best-estimate analysis of an AP600 no-break scenario with WCOBRA/TRAC
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:6982087
- Westinghouse Electric Corp., Pittsburgh, PA (United States)
The WCOBRA/TRAC code is a best-estimate thermal hydraulic code for the evaluation of consequences of a large-break loss-of-coolant accident. The code has been applied to a smalll-break analysis of the most limiting small-break scenario of an AP600 plant. For this purpose, a series of performance tests of the code and models was carried out on key components such as the pressurizer, the core makeup tank (CMT), and the hot- and cold-leg pipes. The hot legs and the cold legs, for example, were modeled with three-dimensional vessel cells so that small-break concerns such as steam/water separation were addressed.
- OSTI ID:
- 6982087
- Report Number(s):
- CONF-921102--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 66
- Country of Publication:
- United States
- Language:
- English
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· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:7118611
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
COMPARATIVE EVALUATIONS
COMPUTER CODES
DEPRESSURIZATION
ENRICHED URANIUM REACTORS
EVALUATION
FLUID MECHANICS
HYDRAULICS
LOSS OF COOLANT
MECHANICS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
T CODES
TESTING
THERMAL ANALYSIS
THERMAL REACTORS
THREE-DIMENSIONAL CALCULATIONS
TRANSIENTS
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
ACCIDENTS
COMPARATIVE EVALUATIONS
COMPUTER CODES
DEPRESSURIZATION
ENRICHED URANIUM REACTORS
EVALUATION
FLUID MECHANICS
HYDRAULICS
LOSS OF COOLANT
MECHANICS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
T CODES
TESTING
THERMAL ANALYSIS
THERMAL REACTORS
THREE-DIMENSIONAL CALCULATIONS
TRANSIENTS
W CODES
WATER COOLED REACTORS
WATER MODERATED REACTORS