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Swelling Control in Uranium Carbide
Author(s) -
ERVIN GUY
Publication year - 1971
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.1151-2916.1971.tb12165.x
Subject(s) - swelling , burnup , materials science , fission , irradiation , tungsten carbide , carbide , tungsten , uranium , radiochemistry , composite material , sintering , chemical engineering , nuclear chemistry , metallurgy , chemistry , neutron , nuclear physics , physics , engineering
Fine particles were dispersed in a fuel structure to trap fission gases as very small bubbles and thereby reduce fuel swelling. The dispersions were made by adding 1.5 to 3.0 wt% W to the UC; the specimens were irradiated to a maximum of ∼2 at.% burnup. Density changes were used as the measure of swelling; there was much scatter in the results. Tungsten reduced the swelling when it was uniformly dispersed. For some samples having excess U and W or a segregated structure, W increased the swelling. The results tentatively confirm that fine particles are of value in reducing fission‐gas swelling of carbide fuels.