International audienceThe growth of a U3O7 oxide layer during the anionic oxidation of UO2 pellets induced very important mechanical stresses due to the crystallographic lattice parameters differences between UO2 and its oxide. These stresses, combined with the chemical processes of oxidation, can lead to the cracking of the system, called chemical fragmentation. We study the crystallographic orientation of the oxide lattice growing at the surface of UO2, pointing the fact that epitaxy relations at interface govern the coexistence of UO2 and U3O7. In this work, several results are given: - Determination of the epitaxy relations between the substrate and its oxide thanks to the Bollmann's method; epitaxy strains are deduced. - Study of the c...
Abstract: The possibility to control oxygen transport in one of the most promising solid oxide fuel ...
International audienceThe principal type of nuclear fuel material, which remains widely used today, ...
The development of residual strains in the iron-oxide layers growing on α-Fe and ε-Fe2N1-z at 673 K ...
International audienceThe growth of a U3O7 oxide layer during the anionic oxidation of UO2 pellets i...
International audienceCracking is observed when a UO2 single crystal is oxidised in air. Previous st...
International audienceThe aim of the present work is to introduce a thermodynamic model to describe ...
This paper offers a study of oxygen dissolution into a solid, and its consequences on the mechanical...
International audienceThe physicochemical properties of uranium are being studied in many applicatio...
In situ HT-ESEM oxidation of sintered UC fragments revealed the morphological changes occurring duri...
Thin oxide films have been used as model supports to unravel the influence of the oxide–metal and ox...
AbstractPressurised and boiling water reactors contain zirconium alloys, which are used as nuclear f...
Spent nuclear fuel is composed of ≈95% UO2, and upon storage in geologic repository the fuel itse...
Abstract: The possibility to control oxygen transport in one of the most promising solid oxide fuel ...
International audienceThe principal type of nuclear fuel material, which remains widely used today, ...
The development of residual strains in the iron-oxide layers growing on α-Fe and ε-Fe2N1-z at 673 K ...
International audienceThe growth of a U3O7 oxide layer during the anionic oxidation of UO2 pellets i...
International audienceCracking is observed when a UO2 single crystal is oxidised in air. Previous st...
International audienceThe aim of the present work is to introduce a thermodynamic model to describe ...
This paper offers a study of oxygen dissolution into a solid, and its consequences on the mechanical...
International audienceThe physicochemical properties of uranium are being studied in many applicatio...
In situ HT-ESEM oxidation of sintered UC fragments revealed the morphological changes occurring duri...
Thin oxide films have been used as model supports to unravel the influence of the oxide–metal and ox...
AbstractPressurised and boiling water reactors contain zirconium alloys, which are used as nuclear f...
Spent nuclear fuel is composed of ≈95% UO2, and upon storage in geologic repository the fuel itse...
Abstract: The possibility to control oxygen transport in one of the most promising solid oxide fuel ...
International audienceThe principal type of nuclear fuel material, which remains widely used today, ...
The development of residual strains in the iron-oxide layers growing on α-Fe and ε-Fe2N1-z at 673 K ...