CERAMIC FUELS

Journal Article · Wed Mar 01 00:00:00 EST 1961 · Bull. inform. sci. et tech. (Paris)

OSTI ID:4064502

Accary, A; Delmas, E

A study of uranium dioxide and uranium monocarbide is presented. The production and sintering of uranium dioxide and the problems connected with the production of highdensity uranium oxide are studied. Some physico-chemical properties of the dioxide are reviewed with respect to the sintering process. The properties of the final products, in particular behavior under irradiation, are described. The application of sintering processes to the production of uranium carbide is described. Some properties of importance with respect to its use as a nuclear fuel, such as thermal conductivity, behavior toward carbon, uranium, and other metals, and the effect of neutron flux, are reported. Possible methods of industrial production are also considered. (auth)

• Research Organization: Originating Research Org. not identified
• NSA Number: NSA-15-021169
• OSTI ID: 4064502
• Journal Information: Bull. inform. sci. et tech. (Paris), Vol. Vol: No. 49; Other Information: Orig. Receipt Date: 31-DEC-61
• Country of Publication: Country unknown/Code not available
• Language: French

Related Subjects

METALS, CERAMICS, AND OTHER MATERIALS
ALL PHYSICAL PROPERTIES
CARBON
CERAMICS
CHEMICAL REACTIONS
DENSITY
FABRICATION
FUELS
IRRADIATION
METALS
NEUTRON FLUX
PRODUCTION
SINTERING
THERMAL CONDUCTIVITY
URANIUM
URANIUM CARBIDES
URANIUM DIOXIDE
URANIUM OXIDES
USES