Evaluation of the SLSF P2 loss-of-flow safety experiment
Conference
·
· Alternative Energy Sources; (United States)
OSTI ID:7155065
An in-reactor safety experiment was performed in the Sodium Loop Safety Facility with a 19-pin, mixed-oxide fuel bundle that simulated a fast reactor accident. Cladding failure and melting, bundle blockage formation, and fuel melting events occurred slightly later than expected. Postirradiation examination data are consistent with accident scenarios in which molten fuel-steel mixtures disperse from the core midplane due to steel vaporization. Approximately 1 s after reactor scram, a fuel-motion event occurred that caused the upward relocation of the upper steel blockage and shroud failure with the ensuing release of a molten fuel-metal mixture from the original fueled region.
- Research Organization:
- Argonne National Laboratory, 9700 S. Cass Ave., Argonne, Illinois
- OSTI ID:
- 7155065
- Report Number(s):
- CONF-801210-
- Journal Information:
- Alternative Energy Sources; (United States), Journal Name: Alternative Energy Sources; (United States) Vol. 5; ISSN ALESD
- 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
ACCIDENTS
ALLOYS
BREEDER REACTORS
COOLANT LOOPS
COOLING SYSTEMS
DETECTION
DISPERSIONS
ENERGY SOURCES
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAILURE MODE ANALYSIS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
FUEL ELEMENT FAILURE
FUEL MOTION DETECTION
FUELS
HEAT TRANSFER
HYDRAULICS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MATERIALS
MECHANICS
MELTING
MIXTURES
MOLTEN SALTS
NUCLEAR FUELS
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR MATERIALS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SALTS
SHROUDS
SIMULATION
STEELS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
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210500 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALLOYS
BREEDER REACTORS
COOLANT LOOPS
COOLING SYSTEMS
DETECTION
DISPERSIONS
ENERGY SOURCES
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAILURE MODE ANALYSIS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
FUEL ELEMENT FAILURE
FUEL MOTION DETECTION
FUELS
HEAT TRANSFER
HYDRAULICS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MATERIALS
MECHANICS
MELTING
MIXTURES
MOLTEN SALTS
NUCLEAR FUELS
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR MATERIALS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SALTS
SHROUDS
SIMULATION
STEELS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TEST FACILITIES
TEST REACTORS