Helium- and sodium-bonded mixed carbide fuels - In-pile behavior and head-end gaseous oxidation

Conference · Sun Jan 01 04:00:00 EST 1989 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6388668

Coquerelle, M; Ronchi, C; Blank, H

This paper reports on a detailed analysis that has been carried out on hyperstoichiometric uranium-plutonium carbide fuel (U{sub 0.8}Pu{sub 0.2}C), which has operated under helium- and sodium-bonded conditions up to 12.5 at.% burnup in a fast flux reactor. The first aspect of the analysis of the fuel was the swelling due to solid and gaseous (including cesium) fission products, coarse porosity, and pellet fracturing. A second aspect of the study included the mechanisms of carbon transfer into the steel cladding and its effects on cladding properties. In the third aspect, examination of the oxidation of carbide fuels was carried out. From this, the most efficient head-end oxidation treatments have been determined for the reprocessing of mixed carbide fuels.

• OSTI ID: 6388668
• Report Number(s): CONF-891103--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 60
• Country of Publication: United States
• Language: English

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ACCIDENTS
ACTINIDE COMPOUNDS
ALKALI METALS
BREEDER REACTORS
BUBBLES
BURNUP
CARBIDES
CARBON COMPOUNDS
CARBURIZATION
CESIUM
CHEMICAL REACTIONS
CRACK PROPAGATION
EFFICIENCY
ELEMENTS
ENERGY SOURCES
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCT RELEASE
FLUIDS
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUELS
GASES
HARDENING
HELIUM
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
METALS
MIXED CARBIDE FUELS
NIOBIUM
NONMETALS
NUCLEAR FUELS
NUCLEATION
OXIDATION
PLUTONIUM CARBIDES
PLUTONIUM COMPOUNDS
POROSITY
RARE GASES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
REPROCESSING
RESEARCH PROGRAMS
SEPARATION PROCESSES
SODIUM
SURFACE HARDENING
SURFACE TREATMENTS
SWELLING
TITANIUM
TRANSITION ELEMENTS
TRANSURANIUM COMPOUNDS
URANIUM CARBIDES
URANIUM COMPOUNDS