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Report No.
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Oxygen potential and oxygen diffusion data for guiding the manufacture of MOX fuel for fast neutron reactors

Vauchy, R.; Horii, Yuta ; Hirooka, Shun ; Akashi, Masatoshi ; Sunaoshi, Takeo*; Nakamichi, Shinya  ; Saito, Kosuke

Controlling the Oxygen/Metal ratio during the sintering of uranium-plutonium mixed oxide fuels is strategic, especially for Fast Neutron Reactors. Within the frame of understanding the reduction of MOX during its sintering, new oxygen potential data and oxygen chemical diffusion coefficients of U$$_{0.698}$$Pu$$_{0.2892}$$Am$$_{0.013}$$O$$_{2-x}$$ were determined by thermogravimetry between 1773 and 1923 K on elongated cylindrical dense pellets. An innovative experimental protocol was developed to correlate oxygen chemical diffusion to Oxygen/Metal ratio ranges, and thus to the underlying defect chemistry. Oxygen self-diffusion coefficients were also obtained by combining the oxygen chemical diffusion coefficients with defect chemistry. These new data provide a better understanding of the mechanisms and kinetics of MOX reduction during its manufacturing as a sodium-cooled fast reactor fuel.

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