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Report No.

Evaluation of thermal conductivity of (U, Pu, Am)O$$_{2-x}$$

Morimoto, Kyoichi ; Kato, Masato   ; Komeno, Akira ; Kashimura, Motoaki

Plutonium and uranium mixed oxide (MOX) fuel with high Pu-content has been developed as a fuel for fast reactors (FRs). Thermal conductivity of the oxide fuel is among the most important properties for design and performance analyses of fuel rods. Among recent reports, there have been none examining of thermal conductivity of MOX fuel containing Am except our studies. In this study, the thermal conductivities of MOX fuel with 30% Pu-content, as obtained by our group, were evaluated as functions of temperature, oxygen-to-metal (O/M) ratio and Am-content.



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