Role of microstructure and surface defects on the dissolution kinetics of CeO2, a UO2 fuel analogue.

The release of radionuclides from spent fuel in a geological disposal facility is controlled by the surface mediated dissolution of UO2 in groundwater. In this study we investigate the influence of reactive surface sites on the dissolution of a synthesised CeO2 analogue for UO2 fuel. Dissolution was performed on: CeO2 annealed at high temperature, which eliminated intrinsic surface defects (point defects and dislocations); CeO2-x annealed in inert and reducing atmospheres to induce oxygen vacancy defects; and on crushed CeO2 particles of different size fractions. BET surface area measurements were used as an indicator of reactive surface site concentration. Cerium stoichiometry, determined using X-ray Photoelectron Spectroscopy (XPS) and supported by X-ray Diffraction (XRD) analysis, was used to determine oxygen vacancy concentration. Upon dissolution in nitric acid medium at 90°C, a quantifiable relationship was established between the concentration of high energy surface sites and CeO2 dissolution rate; the greater the proportion of intrinsic defects and oxygen vacancies, the higher the dissolution rate. Dissolution of oxygen vacancy-containing CeO2-x gave rise to rates that were an order of magnitude greater than for CeO2 with fewer oxygen vacancies. While enhanced solubility of Ce3+ influenced the dissolution, it was shown that replacement of vacancy sites by oxygen significantly affected the dissolution mechanism due to changes in the lattice volume and strain upon dissolution and concurrent grain boundary decohesion. These results highlight the significant influence of defect sites and grain boundaries on the dissolution kinetics of UO2 fuel analogues and reduce uncertainty in the long-term performance of spent fuel in geological disposal

Molten salt synthesis of Ce doped zirconolite for the immobilisation of pyroprocessing wastes and separated plutonium

Molten salt mediated synthesis of zirconolite Ca0.9Zr0.9Ce0.2Ti2O7 was investigated, as a target ceramic matrix for the clean-up of waste molten salts from pyroprocessing of spent nuclear fuels and the immobilisation of separated plutonium. A systematic study of reaction variables, including, reaction temperature, time, atmosphere, reagents and composition, was made to optimise the yield of the target zirconolite phase. Zirconolite 2 M and 3T polytypes were formed as the major phase (with minor perovskite) between 1000 – 1400 °C, in air, with the relative proportion of 2 M polytype increasing with temperature. Synthesis under 5% H2/N2 or Ar increased the proportion of minor perovskite phase and reduced the yield of the zirconolite phase. The yield of zirconolite polytypes was maximised with the addition of 10 wt% TiO2 and 5 wt% TiO2, yielding 91.7 ± 2.0 wt% zirconolite, primarily as the 2 M polytype, after reaction at 1200 °C for 2 h, in air. The particle size and morphology of the zirconolite product bears a close resemblance to that of the TiO2 precursor, demonstrating a dominant template growth mechanism. Although the molten salt mediated synthesis of zirconolite is effective at lower reaction temperature and time, compared to reactive sintering, this investigation has demonstrated that the approach does not offer any clear advantage with over conventional reactive sintering for the envisaged application

Contrôle microstructural des réactions rédox à l'interface solide/solution lors de la dissolution d'oxydes mixtes à base d'uranium (IV)

In the field of the use of actinides mixed oxides as potential fuels for the Gen(III) and Gen(IV) nuclear reactors, solid solutions with general formula U1-xThxO2, U1-xCexO2-y, U0.75Nd0.25O1.875, U0.75Gd0.25O1.875 and Th0.75Nd0.25O1.875 were prepared by thermal conversion of oxalate precursors. Dense pellets exhibiting various physico-chemical and microstructural properties (in terms of composition, homogeneity, densification rate, …) were prepared through sintering then submitted to dissolution tests.The multiparametric study of the dissolution, performed in nitric, sulfuric and hydrochloric media clearly underlined the important effect of the chemical composition on the chemical durability of the samples. Indeed, several parameters (including partial order related to proton activity, apparent activation energy) confirmed the significant modification of the preponderant dissolution mechanism for uranium-enriched samples. Moreover, the role of various nitrogen-based species was evidenced at the solid/solution interface.The evolving of solid/solution interfaces (reactive surface area, composition) during dissolution was monitored by the means of operando ESEM experiments. Preferential dissolution zones (triple junctions, grain boundaries, inter- and intra-granular porosities) were clearly observed for uranium-depleted samples. They induce a significant increase of the reactive surface area even for short progress of the reaction. On the contrary, the dissolution appeared more homogenous for uranium-enriched samples due to the existence of a preponderant mechanism associated to the oxidation of the uranium(IV) at the interface.Dans le cadre de l’utilisation potentielle d’oxydes mixtes d’actinides au sein des réacteurs nucléaires de 3ème et 4ème générations, des solutions solides de formules générales U1-xThxO2, U1-xCexO2-y, U0,75Nd0,25O1,875, U0,75Gd0,25O1,875 et Th0,75Nd0,25O1,875 ont été préparées par conversion thermique de précurseurs oxalate. Préalablement à l’évaluation de la durabilité chimique des matériaux, une étape de frittage a été entreprise afin d’obtenir des pastilles denses présentant diverses propriétés physico-chimiques et microstructurales d’intérêt (composition, homogénéité, taux de densification, …) L’étude multiparamétrique de la dissolution, conduite en milieux nitrique, sulfurique et chlorhydrique a souligné l’impact important de la composition chimique au sein du matériau sur la durabilité chimique des échantillons. En effet, plusieurs paramètres (ordres partiels par rapport à l’activité en protons, énergie d’activation apparente, …) ont confirmé une modification significative du mécanisme de dissolution prépondérant pour les échantillons enrichis en uranium. Par ailleurs, le rôle important joué par certaines espèces azotées à l’interface solide/solution a également été démontré. L’évolution de l’interface solide/solution (surface réactive, composition) en cours de dissolution a également été suivie à travers une étude operando par Microscopie Electronique à Balayage en mode Environnemental. Cette étude a souligné l’existence de zones préférentielles de dissolution (jonctions triples, joints de grains, porosités inter- et intragranulaires) pour les échantillons les moins riches en uranium ; laquelle s’accompagne d’une forte augmentation de la surface réactive. En raison d’un phénomène prépondérant d’oxydation de l’uranium(IV) à l’interface, la dissolution des échantillons enrichis en uranium apparaît nettement plus homogène

Microstructural control of redox reactions at the solid/solution interface during the dissolution of uranium (IV) - based mixed oxides

Dans le cadre de l’utilisation potentielle d’oxydes mixtes d’actinides au sein des réacteurs nucléaires de 3ème et 4ème générations, des solutions solides de formules générales U1-xThxO2, U1-xCexO2-y, U0,75Nd0,25O1,875, U0,75Gd0,25O1,875 et Th0,75Nd0,25O1,875 ont été préparées par conversion thermique de précurseurs oxalate. Préalablement à l’évaluation de la durabilité chimique des matériaux, une étape de frittage a été entreprise afin d’obtenir des pastilles denses présentant diverses propriétés physico-chimiques et microstructurales d’intérêt (composition, homogénéité, taux de densification, …) L’étude multiparamétrique de la dissolution, conduite en milieux nitrique, sulfurique et chlorhydrique a souligné l’impact important de la composition chimique au sein du matériau sur la durabilité chimique des échantillons. En effet, plusieurs paramètres (ordres partiels par rapport à l’activité en protons, énergie d’activation apparente, …) ont confirmé une modification significative du mécanisme de dissolution prépondérant pour les échantillons enrichis en uranium. Par ailleurs, le rôle important joué par certaines espèces azotées à l’interface solide/solution a également été démontré. L’évolution de l’interface solide/solution (surface réactive, composition) en cours de dissolution a également été suivie à travers une étude operando par Microscopie Electronique à Balayage en mode Environnemental. Cette étude a souligné l’existence de zones préférentielles de dissolution (jonctions triples, joints de grains, porosités inter- et intragranulaires) pour les échantillons les moins riches en uranium ; laquelle s’accompagne d’une forte augmentation de la surface réactive. En raison d’un phénomène prépondérant d’oxydation de l’uranium(IV) à l’interface, la dissolution des échantillons enrichis en uranium apparaît nettement plus homogène.In the field of the use of actinides mixed oxides as potential fuels for the Gen(III) and Gen(IV) nuclear reactors, solid solutions with general formula U1-xThxO2, U1-xCexO2-y, U0.75Nd0.25O1.875, U0.75Gd0.25O1.875 and Th0.75Nd0.25O1.875 were prepared by thermal conversion of oxalate precursors. Dense pellets exhibiting various physico-chemical and microstructural properties (in terms of composition, homogeneity, densification rate, …) were prepared through sintering then submitted to dissolution tests.The multiparametric study of the dissolution, performed in nitric, sulfuric and hydrochloric media clearly underlined the important effect of the chemical composition on the chemical durability of the samples. Indeed, several parameters (including partial order related to proton activity, apparent activation energy) confirmed the significant modification of the preponderant dissolution mechanism for uranium-enriched samples. Moreover, the role of various nitrogen-based species was evidenced at the solid/solution interface.The evolving of solid/solution interfaces (reactive surface area, composition) during dissolution was monitored by the means of operando ESEM experiments. Preferential dissolution zones (triple junctions, grain boundaries, inter- and intra-granular porosities) were clearly observed for uranium-depleted samples. They induce a significant increase of the reactive surface area even for short progress of the reaction. On the contrary, the dissolution appeared more homogenous for uranium-enriched samples due to the existence of a preponderant mechanism associated to the oxidation of the uranium(IV) at the interface

Dissolution of uranium mixed oxides: The role of oxygen vacancies vs the redox reactions

International audienc

Modelling of U0.73Pu0.27O2 radiolytic dissolution as a simulant of the alteration of MOX fuel matrices in an underground disposal cell

International audienc

Modeling of the oxidative leaching of U0.73Pu0.27O2 in synthetic clay groundwater with metallic iron

International audienc

Full reactive transport model of U0.73Pu0.27O2 experimental leaching in synthetic clay groundwater with metallic iron

International audienc

Impact of the cationic homogeneity on Th0.5U0.5O2 densification and chemical durability

International audienceIn order to study the effects of cationic homogeneity on the life cycle of Th1-xUxO2 ceramics, including sintering and reprocessing (dissolution) steps, five different ways of preparation were set up, going from the most homogenous oxalic co-precipitation to a mechanical mixture of the parent oxides. Dilatometric experiments evidenced a better sintering capability for the most homogenous compounds obtained through wet chemistry methods while dry chemistry routes led to poor density values (between 80 and 90 %TD). However, the introduction of an additional mechanical grinding step prior to the powders sintering systematically led to the homogenization of the systems. Improved homogeneity also provide a better chemical durability associated with the congruent release of thorium and uranium in solution during dissolution tests of Th0.5U0.5O2 samples. However, heterogeneous samples led to incongruent behaviors that can be lowered by introducing a grinding step before the sintered samples preparation. Since the impact of the cationic homogeneity must be followed carefully during dissolution, in operando observations of evolving solid/solution interface by ESEM were performed. They allowed imaging the preferential dissolution of uranium-enriched zones and confirmed the significant impact over dissolution rate of the presence of chemical heterogeneities at the interface

Dissolution of Th1−xUxO2 : Effects of chemical composition and microstructure

International audienc