Showing 118 results for Author: Annabelle G. Le Coq
Apr, 2026
ORNL Report
This report documents post-irradiation examination (PIE) activities performed in FY 2025 at Oak Ridge National Laboratory on chromium-coated (Cr-coated) and uncoated advanced zirconium alloy claddings irradiated in the High Flux Isotope Reactor (HFIR) to approximately 4 displacements per atom (dpa), corresponding to ~40 GWd/t burnup. Specimens were prepared in axial tensio…
Apr, 2026
ORNL Report
Apr, 2026
ORNL Report
Apr, 2026
Journal
Uranium Nitride (UN) is considered as a possible driver fuel for a variety of advanced reactor designs; however, its qualification remains limited by the lack of consistent, high-quality irradiation performance data. To address this gap, the ROADRUNNER (Research On ADvancing the peRformance of UraNium Nitrides in Extreme enviRonments) irradiation campaign leveraging the Mi…
Apr, 2026
ORNL Report
Advanced nuclear power technologies will use higher temperatures as a means to extract energy at a higher efficiency than current plants and therefore put a larger demand on the structural materials. Improved performance of structural materials could enable greater safety margins, longer plant lifetimes, and reduce maintenance costs. Alloy 709 is championed as the next gen…