Oxide dispersion strengthened steel (ODS) and commercial ferritic-martensitic (F-M) alloys are widely accepted candidate structural materials for designing advanced nuclear reactors. Nanoclusters embedded in the steel matrix are key microstructural features of both alloy types. Irradiation from nuclear fusion and fission affects the morphology of these nanoparticles, altering the performance of the alloys and potentially decreasing their usable lifetime. Thus, it is important to understand the effect of irradiation on these nanoparticles in order to predict long-term nuclear reactor performance. It was found that the evolution of nanoclusters in each material is different depending on the experimental irradiation parameters. The Nelson-Huds...
This study concerns four high performance structural alloys designed to withstand the extreme temper...
Future generation IV nuclear reactors are expected to meet the standards of enhanced safety, minimal...
Reduced-activation ferritic steels are considered as the primary candidate materials for structural ...
The objective of this study is to evaluate the mechanism of irradiation-induced nanoparticle evoluti...
With the rising global demand for low-cost clean energy, nuclear fission and fusion systems willbeco...
International audienceOxide Dispersion Strengthened (ODS) ferritic steels are considered as promisin...
The growing global demand for energy will increasingly call upon fusion reactors and Generation IV n...
A model Fe-9%Cr oxide dispersion strengthened (ODS) steel was irradiated with protons or neutrons to...
The objective of this dissertation is to characterize, and model irradiation-induced solute clusteri...
International audienceDisruption of phase stability by energetic particle bombardment is a major cha...
Oxide Dispersion Strengthened (ODS) steels with nano-scale oxides have become one of the candidate m...
Oxide dispersion strengthened (ODS) ferritic steels are considered promising candidates as cladding ...
This study concerns four high performance structural alloys designed to withstand the extreme temper...
Future generation IV nuclear reactors are expected to meet the standards of enhanced safety, minimal...
Reduced-activation ferritic steels are considered as the primary candidate materials for structural ...
The objective of this study is to evaluate the mechanism of irradiation-induced nanoparticle evoluti...
With the rising global demand for low-cost clean energy, nuclear fission and fusion systems willbeco...
International audienceOxide Dispersion Strengthened (ODS) ferritic steels are considered as promisin...
The growing global demand for energy will increasingly call upon fusion reactors and Generation IV n...
A model Fe-9%Cr oxide dispersion strengthened (ODS) steel was irradiated with protons or neutrons to...
The objective of this dissertation is to characterize, and model irradiation-induced solute clusteri...
International audienceDisruption of phase stability by energetic particle bombardment is a major cha...
Oxide Dispersion Strengthened (ODS) steels with nano-scale oxides have become one of the candidate m...
Oxide dispersion strengthened (ODS) ferritic steels are considered promising candidates as cladding ...
This study concerns four high performance structural alloys designed to withstand the extreme temper...
Future generation IV nuclear reactors are expected to meet the standards of enhanced safety, minimal...
Reduced-activation ferritic steels are considered as the primary candidate materials for structural ...