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Silica‐Uranium Fuel Systems
Author(s) -
CASHIN W. M.
Publication year - 1959
Publication title -
journal of the american ceramic society
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.9
H-Index - 196
eISSN - 1551-2916
pISSN - 0002-7820
DOI - 10.1111/j.1151-2916.1959.tb14318.x
Subject(s) - uranium , uranium oxide , softening point , materials science , softening , fission products , oxide , irradiation , radiochemistry , melting point , glass melting , nuclear fission product , metallurgy , mineralogy , chemistry , composite material , nuclear physics , physics
Presented are the irradiation results on two uranium‐silica systems: a uranium oxide Vycor‐brand glass system and a 10% uranium oxide glass prepared by melting. The glasses were irradiated up to 15% depletion of the uranium at temperatures up to the softening points with no appreciable loss of fission‐product gases. Included is an outline of a procedure for impregnating leached, unfired Vycor‐brand glass with uranium.