International audienceIn the framework of the geological repository of the used fuel claddings of pressurized water reactor, carbon behavior in bulk zirconium is studied by periodic Density Functional Theory calculations. The C interstitial sites were investigated and it was found that there are two possible carbon interstitial sites: a distorted basal tetragonal site and an octahedral site. There are four types of possible atomic jumps between them. After calculating the migration energies, the attempt frequencies and the jump probabilities for each possible migration path, kinetic Monte Carlo (KMC) simulations were performed to simulate carbon diffusion at the macroscopic scale. The results show that carbon diffusion in pure Zr bulk is ex...
International audienceUsing Density Functional Theory with hybrid functionals, we calculate the inte...
AbstractThe diffusion rate of hydrogen in zirconium oxides comes into play in both the steam oxidati...
Le Zirconium, sous forme d alliage, est l élément principal du gainage combustible des réacteurs nuc...
Dans le cadre de la gestion des déchets nucléaires, les coques et embouts des gaines de combustibles...
The current research presents an approach which is used to determine the diffusivity of hydrogen in ...
The diffusion coefficient of insoluble carbon in zirconium oxides has been obtained for the temperat...
International audienceDuring the corrosion in primary water of zirconium, hydrogen from the water di...
International audienceTo better understand the microstructural evolution of Cr-coated Zr alloy cladd...
Zirconium and its alloys are widely used in the nuclear industry. Under normal conditions, Zr-alloys...
Zirconium alloys are the major fuel cladding materials in current reactors. The water-side corrosion...
The formation energies, diffusion barriers, and vibration frequencies of complex iodine defects in z...
In this study, we are interested in the release of carbon in CSD-C (Standard Package of Compacted Wa...
We revisit the ultra-fast diffusion characteristics of Fe, Co, Ni, and Cu solutes, in the hcp hosts ...
Dans cette étude, nous nous intéressons au relâchement du carbone dans les CSD-C (Colis Standard de ...
Transport of point defects controls a variety of materials process such as precipitation, segregatio...
International audienceUsing Density Functional Theory with hybrid functionals, we calculate the inte...
AbstractThe diffusion rate of hydrogen in zirconium oxides comes into play in both the steam oxidati...
Le Zirconium, sous forme d alliage, est l élément principal du gainage combustible des réacteurs nuc...
Dans le cadre de la gestion des déchets nucléaires, les coques et embouts des gaines de combustibles...
The current research presents an approach which is used to determine the diffusivity of hydrogen in ...
The diffusion coefficient of insoluble carbon in zirconium oxides has been obtained for the temperat...
International audienceDuring the corrosion in primary water of zirconium, hydrogen from the water di...
International audienceTo better understand the microstructural evolution of Cr-coated Zr alloy cladd...
Zirconium and its alloys are widely used in the nuclear industry. Under normal conditions, Zr-alloys...
Zirconium alloys are the major fuel cladding materials in current reactors. The water-side corrosion...
The formation energies, diffusion barriers, and vibration frequencies of complex iodine defects in z...
In this study, we are interested in the release of carbon in CSD-C (Standard Package of Compacted Wa...
We revisit the ultra-fast diffusion characteristics of Fe, Co, Ni, and Cu solutes, in the hcp hosts ...
Dans cette étude, nous nous intéressons au relâchement du carbone dans les CSD-C (Colis Standard de ...
Transport of point defects controls a variety of materials process such as precipitation, segregatio...
International audienceUsing Density Functional Theory with hybrid functionals, we calculate the inte...
AbstractThe diffusion rate of hydrogen in zirconium oxides comes into play in both the steam oxidati...
Le Zirconium, sous forme d alliage, est l élément principal du gainage combustible des réacteurs nuc...