Accident progression for a loss-of-heat-sink with scram in a liquid-metal fast breeder reactor

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

OSTI ID:6110784

Bari, R A; Ludewig, H; Pratt, W T; Sun, Y H

An analysis of a slow core meltdown in a liquid-metal fast breeder reactor was performed for the conditions of loss-of-heat-sink following neutronic shutdown. Simple models were developed for the prediction of phase changes and/or relocation of the core materials, including fuel, coolant, cladding ducts, control rod absorber material (B/sub 4/C), and plenum gases. The sequence of events was accounted for, and the accident progression was described up to the point of recriticality. The neutronic behavior of the disrupted core was analyzed in r-z geomertry with a static transport they code (TWOTRAN). For most scenarios assessed, the reactor is expected to become recritical, although large ramp rates are not anticipated.

• Research Organization: Brookhaven National Lab., Upton, NY
• OSTI ID: 6110784
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 44:3; ISSN NUTYB
• Country of Publication: United States
• Language: English

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
ACCIDENTS
AFTER-HEAT REMOVAL
BREEDER REACTORS
CLINCH RIVER BREEDER REACTOR
COMPUTER CALCULATIONS
CRITICALITY
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT SINKS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATHEMATICAL MODELS
MELTDOWN
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR CORES
REACTOR SHUTDOWN
REACTORS
REMOVAL
SCRAM
SHUTDOWNS
SODIUM COOLED REACTORS