Multi-scale structural investigation of uranium-plutonium mixed oxides (U1-yPuy)O2-x with high plutonium content

Uranium-Plutonium mixed oxides U1-yPuyO2-x are considered as the reference fuels for Sodium-cooled Fast neutron Reactors (SFRs). Nevertheless, there is a lack of experimental data on their thermal properties for a Pu content above 0.45. The first step to fill this gap is to manufacture samples with...

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Veröffentlicht in:	Journal of nuclear materials 2023-11, Vol.585, p.154645, Article 154645
Hauptverfasser:	Desagulier, M-M., Martinez, J., Martin, P.M., Lebreton, F., Guéneau, C., Clavier, N.
Format:	Artikel
Sprache:	eng
Schlagworte:	Chemical Sciences Chracterizations Co-milling Manufacturing Material chemistry Mixed-oxides
Online-Zugang:	Volltext
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