Caleb P Massey R&D Associate Staff Member, Advanced Fuel Fabrication and Instrumentation Contact 865.341.0122 | masseycp@ornl.gov All Publications Step-loaded creep testing of Zircaloy-4 cladding at higher temperatures in the α-phase Interface stability of ultrasonic additively manufactured Zircaloy-4 during hydrothermal corrosion High Plasticity in Refractory Composite Fabrication by Ultrasonic Additive Manufacturing Hydrogen embrittlement of Zircaloy-4 fabricated by ultrasonic additive manufacturing MECHANICAL BEHAVIOR OF FRESH, HYDRIDED, AND Cr-COATED CLADDING TUBES AND SUB-SIZED FLAT SPECIMENS Report Summarizing the Mechanical Properties of a Large ODS Ferritic Alloy Ingot by Forging at High Temperatures for Future Mother Tube Production Strength stability at high temperatures for additively manufactured alumina forming austenitic alloy Mini-99 Experiment Design and Target Assembly Effect of Cr content on the hydrothermal corrosion behavior of FeCrAl alloys Post-irradiation examination of commercial tantalum alloys following neutron irradiation High-temperature steam oxidation study of irradiated FeCrAl defueled specimens... Nanostructured Alumina Forming Austenitic Alloy (NAFA) production using mechanical alloying and high-temperature consolidation Status report on HFIR irradiation of optimized alumina forming alloys Characterization of Large Batch 14YWT Heat (NFA-2) for JOYO Irradiations... FeCrAl fuel/clad chemical interaction in light water reactor environments Microstructure dependent burst behavior of oxide dispersion–strengthened FeCrAl cladding Progress on Design and Production of Oxide Dispersion–Strengthened Alumina-Forming Austenitic Alloys for Nuclear Applications Progress on Producing an ODS Ferritic Alloy by High Deformation Processing of Reactive Powders AFC FY 2023 HFIR Irradiation Test Matrix – Supported by the Design of a Ring Specimen Irradiation Vehicle Mechanical properties of Zircaloy cladding tubes and contributions to M.E.T.A. mechanical property database AMMT FY23 HFIR Irradiation Test Matrix – Supported by the Design of a Miniature Bend Bar Irradiation Vehicle Preliminary Report on Compositional Specification for Printed 316SS High temperature creep model development using in-situ 3-D DIC techniques during a simulated LOCA transient Analysis of orientation-dependent deformation mechanisms in additively manufactured Zr using in-situ micromechanical testing: Twinning and orientation gradient High-Temperature Creep Behavior of Thin-Walled FeCrAl Alloy Tubes Pagination Current page 1 Page 2 Page 3 Next page ›› Last page Last » Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Fuel Development Section Fuel Cladding and Core Internals Group
