Thermal Diffusion of Oxygen in PuO2-y
- 1 February 1976
- journal article
- research article
- Published by Taylor & Francis in Nuclear Technology
- Vol. 28 (2) , 256-260
- https://doi.org/10.13182/nt76-a31566
Abstract
Oxygen redistribution in hypostoichiometric plutonium-dioxide has been investigated in out-of-pile experiments. The heat of transport of oxygen thermal diffusion depends on the O/Pu ratio and increases from 0 to -28 kcal/mole when the O/Pu ratio increases from 1.65 to 1.95. The result is comparable to that obtained with mixed oxides, thus indicating the heat of transport of solid-state thermal diffusion to be independent of plutonium concentration in the mixed oxide.Keywords
This publication has 8 references indexed in Scilit:
- Oxygen potential of irradiated urania-plutonia fuel pinsJournal of Nuclear Materials, 1973
- Mesures de resistivite et de cinetique d'oxydation dans PuO2−xJournal of Nuclear Materials, 1973
- Redistribution of plutonium and uranium in mixed (U, Pu) oxide fuel materials in a thermal gradientJournal of Nuclear Materials, 1971
- An investigation in the americium oxide systemJournal of Nuclear Materials, 1970
- Thermal diffusion in closed oxide fuel systemsJournal of Nuclear Materials, 1969
- Effect of a temperature gradient on the stoichiometry of urania-plutonia fuelJournal of Nuclear Materials, 1969
- Phase relationships in the americium-oxygen systemJournal of Inorganic and Nuclear Chemistry, 1968
- Über die oxyde des cers—VJournal of Inorganic and Nuclear Chemistry, 1960