International audienceSeveral (U$_{1-x}$Pu$_x$)O$_{2±δ}$ powders with different morphologies and different plutonium contents were synthetized using a sol-gel route. All the powders were fully characterized to quantify their structural parameters. After understanding and verification of the morphological effects on mixed oxide dissolution, this study consists of quantification of effect of plutonium content on dissolution kinetics using nitric acid 8.5 M at 95 °C. Significant differences in dissolution kinetics were observed. Indeed, the plutonium content is a key parameter that has to be considered in studies of (U$_{1-x}$Pu$_x$)O$_{2±δ}$ dissolution kinetics. A kinetics law was established and validated for dissolutions within these parti...
International audienceUranium dioxide containing 3 mol.% platinum group metals (PGMs) (Ru, Rh, Pd) w...
This article draws a state of knowledge of the dissolution of uranium dioxide in nitric acid media. ...
The reprocessing of spent nuclear fuel is a very important step in the nuclear fuel cycle and one of...
International audienceSeveral (U$_{1-x}$Pu$_x$)O$_{2±δ}$ powders with different morphologies and dif...
AbstractThe focus of this paper is the chemistry of mixed uranium plutonium oxide (MOx,) in nitric a...
Le principal objectif de cette étude est d'acquérir des données de base sur la dissolution de compos...
International audienceStudies dedicated to the chemical durability of spent nuclear fuel are usually...
A series of characterization and dissolution studies has been performed to define flowsheet conditio...
International audienceSeveral UO2 powders with different morphologies were synthetized and character...
AbstractThe effects of Pu content on the dissolution rate and the mass of the insoluble residue of i...
International audienceSodium fast nuclear reactors might operate with MOX fuels containing up to 45%...
International audienceUO2 pellets were prepared by densification of oxides obtained from the convers...
Effective dissolution of plutonium dioxide has traditionally been accomplished by contact with stron...
International audienceUranium dioxide containing 3 mol.% platinum group metals (PGMs) (Ru, Rh, Pd) w...
This article draws a state of knowledge of the dissolution of uranium dioxide in nitric acid media. ...
The reprocessing of spent nuclear fuel is a very important step in the nuclear fuel cycle and one of...
International audienceSeveral (U$_{1-x}$Pu$_x$)O$_{2±δ}$ powders with different morphologies and dif...
AbstractThe focus of this paper is the chemistry of mixed uranium plutonium oxide (MOx,) in nitric a...
Le principal objectif de cette étude est d'acquérir des données de base sur la dissolution de compos...
International audienceStudies dedicated to the chemical durability of spent nuclear fuel are usually...
A series of characterization and dissolution studies has been performed to define flowsheet conditio...
International audienceSeveral UO2 powders with different morphologies were synthetized and character...
AbstractThe effects of Pu content on the dissolution rate and the mass of the insoluble residue of i...
International audienceSodium fast nuclear reactors might operate with MOX fuels containing up to 45%...
International audienceUO2 pellets were prepared by densification of oxides obtained from the convers...
Effective dissolution of plutonium dioxide has traditionally been accomplished by contact with stron...
International audienceUranium dioxide containing 3 mol.% platinum group metals (PGMs) (Ru, Rh, Pd) w...
This article draws a state of knowledge of the dissolution of uranium dioxide in nitric acid media. ...
The reprocessing of spent nuclear fuel is a very important step in the nuclear fuel cycle and one of...