Analysis of FLECHT and FLECHT-SEASET reflood tests with RELAP5/MOD2
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:5348992
Simulations of FLECHT and FLECHT-SEASET unblocked forced flow reflood tests, were performed using RELAP5/MOD2 code reflood capabilities. The predictions of the high flooding injection rate and steam cooling tests were in good agreement with the measurements. The low flooding rate tests showed a tendency to predict lower peak cladding temperatures than the data and unrealistic void fraction oscillations. The spikes in void fraction histories were flow-regime dependent. The prediction for the quench times at the upper bundle elevations was overestimated.
- Research Organization:
- The Babcock and Wilcox Co., Nuclear Power Div., P.O. Box 10935, Lynchburg, VA 24506-0935
- OSTI ID:
- 5348992
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 74:2; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
Similar Records
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Conference
·
Tue Dec 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6883189
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·
Tue Sep 01 00:00:00 EDT 1981
·
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OSTI ID:5497692
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BENCH-SCALE EXPERIMENTS
COMPUTER CODES
COMPUTERIZED SIMULATION
COOLING
ECCS
ENGINEERED SAFETY SYSTEMS
FLOW RATE
FUEL CANS
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
HIGH PRESSURE COOLANT INJECTION
LOSS OF COOLANT
OSCILLATIONS
QUENCHING
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR PROTECTION SYSTEMS
RESEARCH PROGRAMS
ROD BUNDLES
SIMULATION
STEAM
TEMPERATURE EFFECTS
TIME DEPENDENCE
VOID FRACTION
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BENCH-SCALE EXPERIMENTS
COMPUTER CODES
COMPUTERIZED SIMULATION
COOLING
ECCS
ENGINEERED SAFETY SYSTEMS
FLOW RATE
FUEL CANS
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
HIGH PRESSURE COOLANT INJECTION
LOSS OF COOLANT
OSCILLATIONS
QUENCHING
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR PROTECTION SYSTEMS
RESEARCH PROGRAMS
ROD BUNDLES
SIMULATION
STEAM
TEMPERATURE EFFECTS
TIME DEPENDENCE
VOID FRACTION