Irradiation Effects on Uc$Sub 2$ Dispersed in Graphite. (Ornl-Mtr-48-1), Interim Report No. 1 Page: 4 of 16
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ABSTRACT
A dispersion of enriched (93 wt % U'") UCa in graphite was irradiated
in the DMTR as a part of the advanced fuels testing program. The fuel was
irradiated to a burnup of 7560 Mwd/T of fueled matrix, with average fission
power densities of 270 and 300 w/cm3.
Preliminary examinations in the hot cell showed no external dimensional
changes to the graphite cans enclosing the fuel cylinders. One fuel cylin-
der showed a 2.4 to 5.1% decrease in diameter and a 3.5% increase in length.
-N1S7 003
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Morgan, J. G. & Osborne, M. F. Irradiation Effects on Uc$Sub 2$ Dispersed in Graphite. (Ornl-Mtr-48-1), Interim Report No. 1, report, August 18, 1960; Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc864273/m1/4/: accessed March 29, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.