All of the UC-PuC powder required for the natural U irradiation specimens, and some of the powder required for the enriched U irradiation specimens was synthesized. All of the natural uranium UC-PuC pellets required were fabrlcated by pressing and sintering, and are being ground to size. The average density of the (U/sub 0.8/Pu/sub 0.2/)C/sub 0.95/ pellets was 12.54 g/cm/ sup 3/ (92.4% of theoretical) and of the (U/sub 0.08/Pu/sub 0.2/)C/sub 0.95/ plus 0.1 wt% Ni pellets was 13.15 g/cm/sup 3 (96.8% of theoretical). Cored pellets were fabricated by pressing and sintering, and the holes are being reamed to size to …
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All of the UC-PuC powder required for the natural U irradiation specimens, and some of the powder required for the enriched U irradiation specimens was synthesized. All of the natural uranium UC-PuC pellets required were fabrlcated by pressing and sintering, and are being ground to size. The average density of the (U/sub 0.8/Pu/sub 0.2/)C/sub 0.95/ pellets was 12.54 g/cm/ sup 3/ (92.4% of theoretical) and of the (U/sub 0.08/Pu/sub 0.2/)C/sub 0.95/ plus 0.1 wt% Ni pellets was 13.15 g/cm/sup 3 (96.8% of theoretical). Cored pellets were fabricated by pressing and sintering, and the holes are being reamed to size to provide a place for an accurately located central thermocouple. The initial clad irradiation specimens were assembled, and the assembly of the first irradiation capsule was started. The test reactor choice was narrowed to ETR and GETR. The GETR is recommended for at least four of the six capsules. (auth)
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Strasser, A. & Taylor, K.Carbide Fuel Development. Progress Report, April 1, 1962 to June 30, 1962,
report,
August 10, 1962;
United States.
(https://digital.library.unt.edu/ark:/67531/metadc1055098/:
accessed January 21, 2026),
University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu;
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