Multi-scale structural investigation of uranium-plutonium mixed oxides (U$_{1-y}$Pu$_y$)O$_{2-x}$ with high plutonium content - Archive ouverte HAL Accéder directement au contenu
Article Dans Une Revue Journal of Nuclear Materials Année : 2023

Multi-scale structural investigation of uranium-plutonium mixed oxides (U$_{1-y}$Pu$_y$)O$_{2-x}$ with high plutonium content

Résumé

Uranium-Plutonium mixed oxides U$_{1-y}$Pu$_y$O$_{2-x}$ 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 high plutonium contents, which is the purpose of this work. Here, the manufacturing of U$_{1-y}$Pu$_y$O$_2$ 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.
Fichier principal
Vignette du fichier
Article Manufacturing - reviewed.pdf (1.46 Mo) Télécharger le fichier
Origine : Fichiers produits par l'(les) auteur(s)

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 (U$_{1-y}$Pu$_y$)O$_{2-x}$ with high plutonium content. Journal of Nuclear Materials, 2023, 585, pp.154645. ⟨10.1016/j.jnucmat.2023.154645⟩. ⟨hal-04276959⟩
12 Consultations
16 Téléchargements

Altmetric

Partager

Gmail Facebook X LinkedIn More