Fuel canister and blockage pin fabrication for SLSF Experiment P4. [LMFBR]
Conference
·
OSTI ID:5757078
As part of its fast breeder reactor safety research program, Argonne National Laboratory (ANL) has conducted an experiment (SLSF Experiment P4) to determine the extent of fuel-failure propagation resulting from the release of molten fuel from one or more heat-generating fuel canisters. The test conditions consisted of 37 full-length FTR fuel pins operating at FTR rated core nominal peak fuel/reduced coolant conditions. Thirty-four of the the fuel pins were prototypical FTR mixed-oxide fuel pins. The other three fuel pins were fabricated with a mid-core section having an enlarged canister containing fully enriched UO/sub 2/. Two of the canisters were cylindrical and one was fluted. The cylindrical canisters were designed to fail and release molten fuel into the 37-pin fuel cluster at near full power.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 5757078
- Report Number(s):
- HEDL-SA-2855-S; CONF-830609-58; ON: DE83017010
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
210900* -- Nuclear Power Plants-- Process Heat Reactors-- (-1987)
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACCIDENTS
ACTINIDE COMPOUNDS
BREEDER REACTORS
CHALCOGENIDES
EPITHERMAL REACTORS
FABRICATION
FAST REACTORS
FBR TYPE REACTORS
FFTF REACTOR
FUEL ASSEMBLIES
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PELLETS
FUEL PINS
IRRADIATION CAPSULES
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
OXIDES
OXYGEN COMPOUNDS
PELLETS
PLUTONIUM COMPOUNDS
PLUTONIUM DIOXIDE
PLUTONIUM OXIDES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SODIUM COOLED REACTORS
TEST FACILITIES
TEST REACTORS
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
210500 -- Power Reactors
Breeding
210900* -- Nuclear Power Plants-- Process Heat Reactors-- (-1987)
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACCIDENTS
ACTINIDE COMPOUNDS
BREEDER REACTORS
CHALCOGENIDES
EPITHERMAL REACTORS
FABRICATION
FAST REACTORS
FBR TYPE REACTORS
FFTF REACTOR
FUEL ASSEMBLIES
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PELLETS
FUEL PINS
IRRADIATION CAPSULES
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
OXIDES
OXYGEN COMPOUNDS
PELLETS
PLUTONIUM COMPOUNDS
PLUTONIUM DIOXIDE
PLUTONIUM OXIDES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SODIUM COOLED REACTORS
TEST FACILITIES
TEST REACTORS
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES