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

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.

Language	:	English
Journal	:	Frontiers in Nuclear Engineering (Internet)
Volume	:	1
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Pages	:	p.1060218_1 - 1060218_18
Publication Year/Month	:	2022/12
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Paper URL	:	https://doi.org/10.3389/fnuen.2022.1060218
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Keywords	:	MOX Fuel; Diffusion Coefficient; Interdiffusion
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Registration No. : AA20220434
JAEA Abstracts No. : 51000128
Paper Submission No. : 26103

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