In connection with a program to study the behavior of punctured fuel elements for the Tokai Atomic Power Reactor, the diffusion coefficient of fission gas in uranium oxide powder formed by CO
2 oxidation of U was determined by post-irradiation experiment, in which the fractional release of fission gas during isothermal heating of the powder was measured. The U was oxidized at 600 ?? and 700 ??, and in both cases the O/U ratio of the oxides, measured gravimetrically, was 2.0. The diffussion coefficients in the oxide powder formed by oxidation at 600 ?? were found to be 1.4× 10
-20, 1.3×10
-19, 1.1×10
-18 and 1.0×10
-17cm
2sec
-1, respectively at 450 ??, 550 ??, 650 ?? and 750 ??, and in the oxide powder formed at 700 ??, 7.4×10
-19 and 3.6×10
-16cm
2sec
-1 at 600 ?? and 700 ??, respectively. Activation energies calculated for the two oxide powders were comparatively low.
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