Studying self-irradiated materials is an ideal means to investigate the effect of the damages on material structure and to better understand the behaviour of irradiated nuclear fuels. In this context, X-ray diffraction, X-ray absorption spectroscopy and transmission electron microscopy have been used to investigate self-irradiation damaged AmO2. Combining these techniques allows studying the microstructure and the variation of the fluorite structure at both short-range and long-range order. Thus, the increase of both interatomic distances and lattice parameter was shown, as well as the presence of nanometer sized He bubbles. As confirmed by the observed high-level of crytallinity, the fluorite structure exhibits a high radiation tolerance, ...
This report summarizes work done after 2 years of a 3-year project. Using analytic electron microsco...
Within the EFTTRA-T4 project a MgAl2O4 based inert matrix fuel for 241Am transmutation was produced ...
A wide range of materials are currently under consideration for use in advanced nuclear fuel cycle a...
International audience238Pu-doped UO2 was characterised periodically to investigate the long-term ef...
The thermal recovery of self-irradiated and damaged U0.80Am0.20O2−x solid solution was studied in si...
International audienceFluorite-related materials are encountered in nuclear applications as both fue...
International audienceRadiation stability is often a key limiting factor in performance of fluorite-...
International audienceOxides with the fluorite-type structure are radiation tolerant materials. They...
International audienceSpent nuclear fuel (SNF) of light water reactors (LWR) is constituted of a mat...
International audienceFluorites and fluorite-related materials are of interest within the nuclear co...
Microstructural changes in a set of commercial grade UO2 fuel samples have been investigated using s...
Lanthanide and actinide oxides, such as CeO2 [cerium dioxide], ThO2 [thorium dioxide], and UO2 [uran...
The nuclear fuel is subjected to high irradiation dose. Then the fuel, uranium dioxide (UO2) with a ...
Radiation damage effects are of primary concern for materials used in nuclear energy production. In ...
International audienceFluorite-structure oxides are radiation-resistant materials making them ideal ...
This report summarizes work done after 2 years of a 3-year project. Using analytic electron microsco...
Within the EFTTRA-T4 project a MgAl2O4 based inert matrix fuel for 241Am transmutation was produced ...
A wide range of materials are currently under consideration for use in advanced nuclear fuel cycle a...
International audience238Pu-doped UO2 was characterised periodically to investigate the long-term ef...
The thermal recovery of self-irradiated and damaged U0.80Am0.20O2−x solid solution was studied in si...
International audienceFluorite-related materials are encountered in nuclear applications as both fue...
International audienceRadiation stability is often a key limiting factor in performance of fluorite-...
International audienceOxides with the fluorite-type structure are radiation tolerant materials. They...
International audienceSpent nuclear fuel (SNF) of light water reactors (LWR) is constituted of a mat...
International audienceFluorites and fluorite-related materials are of interest within the nuclear co...
Microstructural changes in a set of commercial grade UO2 fuel samples have been investigated using s...
Lanthanide and actinide oxides, such as CeO2 [cerium dioxide], ThO2 [thorium dioxide], and UO2 [uran...
The nuclear fuel is subjected to high irradiation dose. Then the fuel, uranium dioxide (UO2) with a ...
Radiation damage effects are of primary concern for materials used in nuclear energy production. In ...
International audienceFluorite-structure oxides are radiation-resistant materials making them ideal ...
This report summarizes work done after 2 years of a 3-year project. Using analytic electron microsco...
Within the EFTTRA-T4 project a MgAl2O4 based inert matrix fuel for 241Am transmutation was produced ...
A wide range of materials are currently under consideration for use in advanced nuclear fuel cycle a...