Download or read book CARBIDE FUEL DEVELOPMENT Progress Report October 1 1962 March 31 1963 written by and published by . This book was released on 1963 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: FUEL FABRlCATlON AND EVALUATION. The synthesis and fabrication of (UO/ sub 0.95/Pu/sub 0.05/)C/sub 0.98/ test specimens by cold pressing and sintering for out-of-pile property measurements were completed. Theoretical densities of 91% (avg) were obtained without sirtering aid and 96% (avg) with 0.1 wt% nickel sintering aid. Mixed sesquicarbide, ated into pellets 94% of theoretical density. Massive, carbon-stabilized PuO was synthesized by the carbon reduction of the dioxide. The carbon content of the product was 0.14 wt%. The coefficients of expansion of (U/sub 0.95/Pu/sub 0.05/)C/sub 0.098/ with and without nickel sintering aid were measured to 1400 deg C, and found to be 12.2 to 12.6 x 10/sup - 6/DEC. Measurements of melting point and vapor pressure of mixed monocarbides were started by testing standards. Compatibility tests at 593 and 816 deg C were started. Examinarion of results to date show a reaction between (U/sub 0.95/Pu/ sub 0.05/)C/sub 0.98/ and Zircaloy-2, and no reaction with type 316 stainless steel and niobium after 1000 hr at 816 deg C. This is similar to previous results with UC. IRRADIATION TESTS. The assembly of all the irradiation capsules was completed. Ten of the 12 planned specimens of (U/sub 0.8/Pu/sub 0.2/) C/sub 0.95/ are currently operating in the GETR. The longest burnup obtained to date is 13,000 Mwd/ton (avg). (auth).

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Download or read book CARBIDE FUEL DEVELOPMENT Progress Report January 1 1962 to March 31 1962 written by and published by . This book was released on 1962 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Reproducibly high density UC-PuC pellets containing minor amounts of (U, Pu)2C3 were made with nickel sintering aid. Average densities of 95% and maximum densities of 96.6% of theoretical were obtained. High density, singlephase UC-PuC pellets were made by sintering at high temperatures. Densities of 94% of theoretical appear to be attainable. Improved identification of microstructural constituents was made by means of metallography, x-ray diffraction, and microprobe analysis. Development of specialized chemical analysis techniques continued. The post-irradiation examination of the UC specimens was completed. Mass spectrometer analysis showed that 0.4% of the fission gases was released. Metallographic examination of the UC did not reveal any channges in structure. Metallographic examination of the metal specimen parts that were in contact with UC was completed. No evidence for interaction with niobium and slight evidence for interaction with stainless steel was found. The latter was not deleterious. Perturbation factors were calculated for the UC- PuC experiments. Negotiations continued, in order to select the most suitable test reactor. (auth).