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Prediction of the CRBRP outlet plenum transient response following a reactor trip

Conference ·
OSTI ID:7321705
; ;
An assessment was made of the ability of a numerical hydro computer code, VARR-II, to accurately predict the transient response of the outlet plenum of the Clinch River Breeder Reactor Plant, following a reactor trip. Analytical model size and representation of the internals, located in the outlet plenum, were varied and a model to represent the outlet plenum was selected. Using this analytical model, the calculated temperature response compared favorably with experimental data, which included the effects of flow stratification following a simulated reactor trip.
OSTI ID:
7321705
Report Number(s):
CONF-770802-5
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BREEDER REACTORS
CLINCH RIVER BREEDER REACTOR
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HYDRODYNAMICS
LIQUID METAL COOLED REACTORS
MECHANICS
POWER REACTORS
REACTOR COMPONENTS
REACTOR INTERNALS
REACTORS
SODIUM COOLED REACTORS
TEMPERATURE DISTRIBUTION
TRANSIENTS