Abstract
Uranium dioxide exhibits a wide range of stoichiometxy with the deviation from stoichiometry, x, ranging from -0.31 to +0.24. The observation of oxygen redistribution in uranium dioxide based fuels in a nuclear reactor and the consequent effect on operational performance parameters, has prompted investigation of the migration of oxygen in a temperature gradient. Several laboratory studies have been conducted on both uranium dioxide and mixed oxide fuels [1–6].
Work supported by the Atomic Energy Commission.
The material reported is part of a thesis submitted by D. D. Marchant in partial fulfillment of the requirements for the degree of Doctor of Science, Department of Metallurgy and Materials Science, M.I.T., Cambridge, Mass.
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Marchant, D.D., Bowen, H.K. (1975). Oxygen Redistribution in UO2 Due to a Temperature Gradient. In: Cooper, A.R., Heuer, A.H. (eds) Mass Transport Phenomena in Ceramics. Materials Science Research, vol 9. Springer, Boston, MA. https://doi.org/10.1007/978-1-4684-3150-6_6
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