Experimental study of scram transients in generalized liquid-metal fast breeder reactor outlet plenums

Journal Article · Sun Jul 01 04:00:00 EDT 1979 · Nucl. Technol.; (United States)

OSTI ID:5947451

Howard, P A; Carbajo, J J

An experimental study was made of the transient behavior of the coolant in a generalized outlet plenum after a scram in a liquid-metal fast breeder reactor. Different conditions of fluid flow rate and temperature and plenum geometry were used for a three-exit loop-type reactor system. Water was used to simulate the coolant, and a small-scale model was used to simulate the various generalized plenum configurations. Thermocouples monitored the temperatures at 48 locations within the outlet plenum. The thermohydraulic behavior within the plenum has been studied in detail; analysis of this behavior is described as having three consecutive discrete stages. Correlations found in the literature accurately predict the height of the negatively buoyant plume. New correlations have been obtained.

• Research Organization: Argonne National Lab., IL
• OSTI ID: 5947451
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 44:2; ISSN NUTYB
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
COOLING SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FLUID MECHANICS
HYDRAULICS
LIQUID FLOW
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SHUTDOWN
REACTORS
SCRAM
SHUTDOWNS
TRANSIENTS