DOE OSTI · 3030407
ATF Cladding Mechanical Properties Report: Capability Demonstration
Abstract
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 tension (ATT) and ring tension (RTT) geometries, and passive silicon carbide thermometry was employed to determine irradiation temperatures, which averaged 38–43 °C below the 330 °C design target.
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Cinbiz, M. Nedim [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000346268515), Garrison, Ben [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000316880682), Blount, Ethan [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0009000959141661), Harp, Jason [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000253458440), Le Coq, Annabelle [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:000000016482690X), Linton, Kory [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000230024623), Capps, Nathan [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)]. 2025-09-01. ATF Cladding Mechanical Properties Report: Capability Demonstration. https://doi.org/10.2172/3030407
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