journal article·2008-08

Applicability of CeO2 as a surrogate for PuO2 in a MOX fuel development

Han Soo Kim, Chang Yong Joung, Byung Ho Lee, Jae Yong Oh, Yang Hyun Koo, Peter Heimgartner

Journal of Nuclear Materials· Volume 378· Issue 1
Publisher page

Abstract

Abstract The applicability of cerium oxide, as a surrogate for plutonium oxide, was evaluated for the fabrication process of a MOX (mixed oxide) fuel pellet. Sintering behavior, pore former effect and thermal properties of the Ce–MOX were compared with those of Pu–MOX. Compacting parameters of the Pu–MOX powder were optimized by a simulation using Ce–MOX powder. Sintering behavior of Ce–MOX was very similar to that of Pu–MOX, in particular for the oxidative sintering process. The sintered density of both pellets was decreased with the same slope with an increasing DA (dicarbon amide) content. Both the Ce–MOX and Pu–MOX pellets which were fabricated by an admixing of 0.05 wt% DA and sintering in a CO2 atmosphere had the same average grain size of 11 μm and a density of 95%T.D. The thermal conductivity of the Pu–MOX was a little higher than that of the Ce–MOX at a lower temperature but both conductivities became closer to each other above 900 K. Cerium oxide was found to be a useful surrogate to simulate the Pu behavior in the MOX fuel fabrication.
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Research context

OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Radioactive element chemistry and processing

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