Fuel/sodium reaction product formation in breached mixed-oxide fuel
Conference
·
· Transactions of the American Nuclear Society; (USA)
OSTI ID:5492998
The run-beyond-cladding-breach (RBCB) operation of mixed-oxide liquid-metal reactor fuel pins has been studied for 6 yr in the Experimental Breeder Reactor II (EBR-II) as part of a joint program between the US Department of Energy and the Power Reactor and Nuclear Fuel Development Corporation of Japan. The formation of fuel-sodium reaction product (FSRP), Na{sub 3}MO{sub 4}, where M = U{sub 1-y}Pu{sub y}, in the outer fuel regions is the major phenomenon governing RBCB behavior. It increases fuel volume, decreases fuel stoichiometry, modifies fission product distributions, and alters thermal performance of a pin. This paper describes the morphology of Na{sub 3}MO{sub 4} observed in 5.84-mm-diam pins covering a variety of conditions and RBCB times up to 150 effective full-power days (EFPDs).
- OSTI ID:
- 5492998
- Report Number(s):
- CONF-881011--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 57
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fuel-sodium reaction product formation in breached mixed-oxide fuel
Long-term RBCB (run-beyond-cladding-breach) operation of a mixed-oxide fuel subassembly in EBR-II (Experimental Breeder Reactor II)
Thermal conductivity of Na/sub 3/(U/sub 1-y/Pu/sub y/O/sub 4/: a preliminary in-pile determination
Conference
·
Thu Dec 31 23:00:00 EST 1987
·
OSTI ID:6520798
Long-term RBCB (run-beyond-cladding-breach) operation of a mixed-oxide fuel subassembly in EBR-II (Experimental Breeder Reactor II)
Conference
·
Sat Dec 31 23:00:00 EST 1988
· Transactions of the American Nuclear Society; (USA)
·
OSTI ID:6528725
Thermal conductivity of Na/sub 3/(U/sub 1-y/Pu/sub y/O/sub 4/: a preliminary in-pile determination
Conference
·
Wed Dec 31 23:00:00 EST 1986
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:7148096
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ACCIDENTS
ACTINIDES
ASIA
BREEDER REACTORS
ELEMENTS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCTS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
FUEL-COOLANT INTERACTIONS
FUELS
HEAT TRANSFER
ISOTOPES
JAPAN
JAPANESE ORGANIZATIONS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
METALS
MIXED OXIDE FUELS
NATIONAL ORGANIZATIONS
NONMETALS
OXYGEN
PERFORMANCE
PLUTONIUM
PNC
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SOLID FUELS
STOICHIOMETRY
TRANSURANIUM ELEMENTS
URANIUM
US DOE
US ORGANIZATIONS
VOLUME
210500* -- Power Reactors
Breeding
ACCIDENTS
ACTINIDES
ASIA
BREEDER REACTORS
ELEMENTS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCTS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
FUEL-COOLANT INTERACTIONS
FUELS
HEAT TRANSFER
ISOTOPES
JAPAN
JAPANESE ORGANIZATIONS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
METALS
MIXED OXIDE FUELS
NATIONAL ORGANIZATIONS
NONMETALS
OXYGEN
PERFORMANCE
PLUTONIUM
PNC
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SOLID FUELS
STOICHIOMETRY
TRANSURANIUM ELEMENTS
URANIUM
US DOE
US ORGANIZATIONS
VOLUME