It has been corfirmed that uranium monocarbide can be prepared by reacting uranium metal powder with methane at about 650 C, and that sintered carbides of greater than 90% of theoretical density can be made. The cast density of carbides has been found to vary from 13.56 g/cm/sup 3/ for UC to 11.7 g/cm/sup 3/ for UC/sub 2/. The electrical resistivity of cast carbides has been found to vary from about 40 microhm-cm for UC to about 90 microhm-cm for UC/sub 2/ . About 500 ppm of iron or silicon has been found to decrease the quality of arc- melted …
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It has been corfirmed that uranium monocarbide can be prepared by reacting uranium metal powder with methane at about 650 C, and that sintered carbides of greater than 90% of theoretical density can be made. The cast density of carbides has been found to vary from 13.56 g/cm/sup 3/ for UC to 11.7 g/cm/sup 3/ for UC/sub 2/. The electrical resistivity of cast carbides has been found to vary from about 40 microhm-cm for UC to about 90 microhm-cm for UC/sub 2/ . About 500 ppm of iron or silicon has been found to decrease the quality of arc- melted castings of uranium monocarbide. Oxygen reacts with molten carbide to produce metal and carbon monoride. Nitrogen seems to react with molten carbide to displace carbon from the monocarbide and produce some dicarbide. Diffusion rates in the carbides have been found to be appreciable at 1600 C (D = 3.6 x 10/sup -8/ cm/sup 2//sec) and very rapid at 1980 C (D = 2.2 x 10/sup -6/ cm/ sup 2/sec). The activation energy for diffusion in this system is very high (92,000 cal/mole). Additional studies are in progress to determine suitable chemical methods of preparing carbides from available raw materials, to develop techniques for making highdensity compacts of carbide powder, to cast large shapes of carbide by melting techniques, to measure the mechanical and physical properties of cast uranium carbide and its alloys, to determine the chemical compatibility of carbides with various metals and reactor coolants, and to obtain information on the mechanism by which carbide-type compounds are damaged by fission fragments during neutron irradiation. (auth)
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Rough, F.A. & Chubb, W. eds.PROGRESS ON THE DEVELOPMENT OF URANIUM CARBIDE-TYPE FUELS,
report,
August 21, 1959;
Columbus, Ohio.
(https://digital.library.unt.edu/ark:/67531/metadc1024004/:
accessed October 7, 2024),
University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu;
crediting UNT Libraries Government Documents Department.
