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

Conference · Thu Jan 01 00:00:00 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; TRN: 77-005641
• Resource Relation: Conference: Annual meeting of the American Society of Mechanical Engineers, New York, NY, USA, 29 Nov 1976
• Country of Publication: United States
• Language: English

Related Subjects

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