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filingDate 1963-09-17-04:00^^<http://www.w3.org/2001/XMLSchema#date>
publicationDate 1967-03-22-04:00^^<http://www.w3.org/2001/XMLSchema#date>
publicationNumber GB-1062875-A
titleOfInvention Nuclear reactor fuel
abstract A previously shaped, sintered and densified mass of hyperstoichiometric dioxide which may be uranium, plutonium, or thorium dioxide or mixtures thereof is treated to produce a hypostoichiometric product which has an improved thermal conductivity compared to the starting material by heating the dioxide material at a temperature above 1500 DEG C. under at least one of the following conditions:-(a) in an oxygen-free gaseous medium maintained substantially oxygen-free throughout the heat treatment; (b) in vacuo; and (c) in the presence of a solid getter (which is not dispersed within said mass). The preferred temperature range is 1500 DEG to 1900 DEG C. and suitable getter materials are exemplified as graphite, Ta, Mo, W, and mixtures thereof. The product, which may, for example, be represented by the formula UO2- x, where x is above zero up and to 0.3, may be used as a fuel element in a nuclear reactor when the element is either constructed of the previously prepared hypostoichiometric oxide, or the hyperstoichiometric oxide is used and the reactor operated so that the necessary above-mentioned deoxygenating conditions obtain. The fuel element may be assembled with a getter material as the core or the end caps of the element and the reactor operated so that the hypostoichiometric nature of the fuel is maintained. A hypostoichiometric oxide as prepared above, for example one having the formula UO1.97- 1.998, may be used as the active element in a thermoelectric device.
priorityDate 1962-10-10-04:00^^<http://www.w3.org/2001/XMLSchema#date>
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