Article ID Journal Published Year Pages File Type
1570100 Journal of Nuclear Materials 2006 6 Pages PDF
Abstract

(U, Pu) mixed oxides, (U1−yPuy)O2−x, with y = 0.21 and 0.28 are being considered as fuels for the Prototype Fast Breeder Reactor (PFBR) in India. The use of urania–plutonia solid solutions in PFBR calls for accurate measurement of physicochemical properties of these materials. Hence, in the present study, oxygen potentials of (U1−yPuy)O2−x, with y = 0.21 and 0.28 were measured over the temperature range 1073–1473 K covering an oxygen potential range of −550 to −300 kJ mol−1 (O/M ratio from 1.96 to 2.000) by employing a H2/H2O gas equilibration technique followed by solid electrolyte EMFmeasurement. (U1−yPuy)O2−x, with y = 0.40 is being used in the Fast Breeder Test Reactor (FBTR) in India to test the behaviour of fuels with high plutonium content. However, data on the oxygen potential as well as thermal conductivity of the mixed oxides with high plutonium content are scanty. Hence, the thermal diffusivity of (U1−yPuy)O2, with y = 0.21, 0.28 and 0.40 was measured and the results of the measurements are reported.

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Physical Sciences and Engineering Energy Nuclear Energy and Engineering
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