Outlet plenum flow stratification studies for the Clinch River Breeder Reactor Plant

Conference · Thu Jan 01 04:00:00 EST 1976

OSTI ID:7335087

Novendstern, E H; Woods, M D; Andreychek, T S; Flannigan, L J; Carr, J A

The transient temperature behavior during a simulated reactor trip was studied in a 1/3 sector, 0.55 scale model of the reactor outlet plenum of the CRBRP. Buoyancy effects were simulated using water and salt solution. Effects of variations in Richardson Number (ratio of buoyancy/inertia forces) and Froude Number (ratio of inertia/viscous forces) were evaluated. Effects of geometrical changes of a component in the outlet plenum called the Upper Internals Structure on transient temperature response were studied; both height of the structure and leakage under this component were experimentally varied. The test results confirm that flow stratification occurs in the outlet plenum following a reactor trip. The colder, denser fluid issuing from the core assemblies during the transient fills the lower portion of the plenum while the hotter fluid is trapped in the region above the outlet nozzles.

• Research Organization: Westinghouse Electric Corp., Madison, PA (USA). Advanced Reactors Div.; Battelle Columbus Labs., OH (USA)
• DOE Contract Number: E(11-1)-2395
• OSTI ID: 7335087
• Report Number(s): CONF-761107-11
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
CLINCH RIVER BREEDER REACTOR
COOLING SYSTEMS
DISTRIBUTION
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
LIQUID METAL COOLED REACTORS
MOCKUP
POWER REACTORS
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SIMULATION
SODIUM COOLED REACTORS
SPATIAL DISTRIBUTION
STRATIFICATION
STRUCTURAL MODELS
TEMPERATURE DISTRIBUTION
TRANSIENTS