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Author Accary, A. ♦ Delmas, E.
Source United States Department of Energy Office of Scientific and Technical Information
Content type Text
Language French
Subject Keyword 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
Abstract 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)
Educational Use Research
Learning Resource Type Article
Publisher Date 1961-03-01
Journal Bull. inform. sci. et tech.
Volume Number 49


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