Publications
Showing 71 results for Author: Ben E. Garrison
Jun, 2026
Conference Paper
Benchmark Mechanical Test Results of Westinghouse Zirconium Cladding and Irradiated Testing Readiness
Apr, 2026
ORNL Report
ATF Cladding Mechanical Properties Report: Capability Demonstration
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
AFC Time-at-Temperature Irradiation Campaign and Post-Irradiation Examination Plan
Mar, 2026
Conference Paper
Mechanical response of HFIR-irradiated M5FRAMATOME cladding under simple and complex loading conditions
This study investigates the mechanical behavior of High Flux Isotope Reactor (HFIR) irradiated M5FRAMATOME cladding under simple and complex loading conditions through axial tensile and reversible cyclic bending. Axial tension specimens were pre-machined prior to HFIR irradiation while cyclic bend specimens were inserted as intact tubes. Tests articles were neutron-irradia…
Mar, 2026
Conference Paper
MECHANICAL BEHAVIOR OF FRESH, HYDRIDED, AND Cr-COATED CLADDING TUBES AND SUB-SIZED FLAT SPECIMENS
Mar, 2026
Conference Paper
Rupture Properties of Hydrided Fuel Cladding During Simulated LOCA Conditions
Mar, 2026
Conference Paper
Irradiation and Mechanical Testing of Chromium-Coated M5Framatome Cladding Tubes