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Article Dans Une Revue Journal of Nuclear Materials Année : 2023

Multi-scale structural investigation of uranium-plutonium mixed oxides (U1yPuy)O2x with high plutonium content

Résumé

Uranium-Plutonium mixed oxides U1yPuyO2x 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 high plutonium contents, which is the purpose of this work. Here, the manufacturing of U1yPuyO2 samples with y = 0.60, 0.65 and 0.70 by a co-milling powder metallurgy process is detailed. Relying on an optimization of each manufacturing step (blending, co-milling, sieving, pelletizing and sintering), in order to obtain dense, monophasic, stoichiometric and homogenous materials. A multi-scale characterization strategy was used to determine sample microstructural properties including density measurements, Thermal-Ionization Mass Spectrometer (TIMS), ceramography, Electron Probe Micro Analyses, µ-Raman Spectroscopy and X-Ray Diffraction. The results obtained show that dense (> 95% TD), homogenous (chemical distribution of cations and oxygen), monophasic and stoichiometric (O/M = 2.00) samples have been achieved. These properties correspond to those needed to optimize the thermo-physical properties measurements. This also shows that the coupling of multi-scale characterizations is mandatory to evaluate the structural and microstructural properties of this kind of material.
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Dates et versions

hal-04276959 , version 1 (09-11-2023)

Identifiants

Citer

M-M. Desagulier, J. Martinez, P.M. Martin, F. Lebreton, C. Guéneau, et al.. Multi-scale structural investigation of uranium-plutonium mixed oxides (U1yPuy)O2x with high plutonium content. Journal of Nuclear Materials, 2023, 585, pp.154645. ⟨10.1016/j.jnucmat.2023.154645⟩. ⟨hal-04276959⟩
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