Caleb 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 Process-Property-Performance Mapping of Additively Manufactured 316H Stainless Steel Components... 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 Characterization of Large Batch 14YWT Heat (NFA-2) for JOYO Irradiations... 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 FeCrAl fuel/clad chemical interaction in light water reactor environments Microstructure dependent burst behavior of oxide dispersion–strengthened FeCrAl cladding AFC FY 2023 HFIR Irradiation Test Matrix – Supported by the Design of a Ring Specimen Irradiation Vehicle 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 Data-Driven Optimization of the Processing Window for 316H Components Fabricated Using Laser Powder Bed Fusion Preliminary Report on Compositional Specification for Printed 316SS 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 High temperature creep model development using in-situ 3-D DIC techniques during a simulated LOCA transient Pagination Current page 1 Page 2 Page 3 … Next page ›â¶Äº 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
