Self healing of early stage radiation damage by site selective solute segregation is a promising approach to extend the lifetime of nuclear reactor components. In the present study, the creation and autonomous healing of irradiation-induced damage is investigated in pure Fe and high purity Fe–Au and Fe–Cu model alloys. To create radiation damage samples are irradiated at 550 °C by 120 keV He+ ions with fluences of 5.0 × 1015, 1.0 × 1016 and 5.0 × 1016 ions/cm2. The observed increase in the S and W parameters determined in the variable energy positron annihilation spectroscopy measurements indicates the formation of vacancy-like defects, precipitates and vacancy-solute complexes. The presence of substitutionally dissolved Au is found to redu...
International audienceVacancy defects in tungsten induced by self-irradiation were characterized by ...
The paper discusses our recent experiments focused on the chromium influence on the microstructural ...
The generation and evolution of open volume defects in underaged and T3 Al-Cu-Mg alloy is studied wi...
The radiation damage is one of the key concerns in the research of materials used in radiation envir...
The effect of thermal aging of homogenized Fe-Au and Fe-Au-W alloys, irradiated at room temperature ...
The degradation of reactor pressure vessel steels under irradiation, which results from the hardenin...
Positron annihilation lifetime measurements and angular correlation measurements have been performed...
This thesis investigates the self-healing mechanisms of deformation-induced defects in ferritic Fe-A...
The recovery process of defects in iron dilute alloys could be strongly affected by small amount of ...
International audienceVacancy defects in tungsten induced by self-ion irradiation were characterized...
Oxide dispersion strengthened steels are candidate materials for nuclear reactor applications due to...
Steel components can exhibit premature and low-ductility creep fracture, when exposed to high temper...
Positrons administer a unique non-destructive approach to probe materials with atomic-scale sensitiv...
It is well known that the recovery of defects in iron alloys is affected by impurity atoms. Especial...
Positron annihilation spectroscopy (PAS) is a powerful, non-destructive technique used to characteri...
International audienceVacancy defects in tungsten induced by self-irradiation were characterized by ...
The paper discusses our recent experiments focused on the chromium influence on the microstructural ...
The generation and evolution of open volume defects in underaged and T3 Al-Cu-Mg alloy is studied wi...
The radiation damage is one of the key concerns in the research of materials used in radiation envir...
The effect of thermal aging of homogenized Fe-Au and Fe-Au-W alloys, irradiated at room temperature ...
The degradation of reactor pressure vessel steels under irradiation, which results from the hardenin...
Positron annihilation lifetime measurements and angular correlation measurements have been performed...
This thesis investigates the self-healing mechanisms of deformation-induced defects in ferritic Fe-A...
The recovery process of defects in iron dilute alloys could be strongly affected by small amount of ...
International audienceVacancy defects in tungsten induced by self-ion irradiation were characterized...
Oxide dispersion strengthened steels are candidate materials for nuclear reactor applications due to...
Steel components can exhibit premature and low-ductility creep fracture, when exposed to high temper...
Positrons administer a unique non-destructive approach to probe materials with atomic-scale sensitiv...
It is well known that the recovery of defects in iron alloys is affected by impurity atoms. Especial...
Positron annihilation spectroscopy (PAS) is a powerful, non-destructive technique used to characteri...
International audienceVacancy defects in tungsten induced by self-irradiation were characterized by ...
The paper discusses our recent experiments focused on the chromium influence on the microstructural ...
The generation and evolution of open volume defects in underaged and T3 Al-Cu-Mg alloy is studied wi...