Caleb Massey R&D Associate Staff Member, Advanced Fuel Fabrication and Instrumentation Contact MASSEYCP@ORNL.GOV All Publications Assessing the viability of a new subsize tensile specimen geometry for evaluation of structural nuclear and additively manufactured materials Recrystallization driven softening and heating rate dependencies of FeCrAl nuclear fuel cladding during accident transients Localized orientation gradients in additively manufactured stainless steel 316H structures Compatibility of Zircaloy-4 in eutectic PbSn and PbBiSn liquid metals Development of Large Bore Rabbit Capsules in Support of BWR Cladding Irradiations in HFIR 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 Viability of miniature discs in LFA-427 Report Summarizing the Mechanical Properties of a Large ODS Ferritic Alloy Ingot by Forging at High Temperatures for Future Mother Tube Production Process-Property-Performance Mapping of Additively Manufactured 316H Stainless Steel Components 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 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
