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- W8699575 abstract "Single-phase solid solution UC-- PuC powders were prepared by the carbon reduction of a mixture of UO/sub 2/ and PuO/sub 2/. A simple method was developed to determine the completion of the reaction by analyzing the exhaust gas from the furnace for CO. Four groups of solid solution (U/sub 0.8/Pu/sub 0.2/ )C/sub 0.95/ pellets were prepared for irradiation tests. The groups differed in the enrichment of uranium and in the presence or absence of nickel sintering aid. Without sintering aid, densities averaged about 92% of theoretical; with sintering aid the average density was about 96% of theoretical. The second phase, promoted by the use of nickel sintering aid, was identified as sesquicarbide. IRRADIATION TESTS. The post-irradiation examination of UC specimens irradiated to 16,400 Mwd/tonne (avg) at 1400 deg F and 9.6 kw./ft was completed. The effect of radiation on UC was slight: 0.001 in. diametral increase, 0.4% fission gas release, and no microstructural changes. The (U/sub 0.8/Pu/sub 0.2/)C/sub 0.95/ irradiation tests were redesigned for insertion in GETR. All the irradiation specimens were assembled, and assembly of the capsules was started. One fueled and one dummy capsule were shipped to the test site. (auth)" @default.
- W8699575 created "2016-06-24" @default.
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- W8699575 date "1963-03-31" @default.
- W8699575 modified "2023-09-23" @default.
- W8699575 title "CARBIDE FUEL DEVELOPMENT. Phase IV Report, September 15, 1961-September 30, 1962" @default.
- W8699575 doi "https://doi.org/10.2172/4685476" @default.
- W8699575 hasPublicationYear "1963" @default.
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