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Cation interdiffusion in uranium-plutonium mixed oxide fuels; Where are we now?

ウラン-プルトニウム混合酸化物燃料の相互拡散; 我々は今どこにいるか?

Vauchy, R.  ; 廣岡 瞬 ; 松本 卓; 加藤 正人   

Vauchy, R.; Hirooka, Shun; Matsumoto, Taku; Kato, Masato

Diffusion phenomena in uranium-plutonium mixed oxides U$$_{1-y}$$PuyO$$_{2}$$ dictate the physicochemical properties of MOX nuclear fuel throughout manufacturing, irradiation and storage. More precisely, estimating the cation interdiffusion is paramount insofar as it dovetails with the actinide redistribution during sintering and under irradiation. In this paper, we propose a critical review of the existing experimental data of U and Pu interdiffusion coefficients in MOX fuel.

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