Caleb Massey R&D Associate Staff Member, Advanced Fuel Fabrication and Instrumentation Contact MASSEYCP@ORNL.GOV All Publications Strength and rupture geometry of un-irradiated C26M FeCrAl under LOCA burst testing conditions Ultrasonic additive manufacturing of zirconium: Pilot results Response of Accident Tolerant Fuel Cladding concepts to LOCA Burst Testing Deformation and fracture characteristics of zirconium plate produced via ultrasonic additive manufacturing FeCrAl Accident Tolerant Fuel Cladding: Insights from a Decade of Development Oxidation Behavior Comparison of UAM and Conventional Zry-4 Assembly of MiniFuel Targets for Irradiation of U-Mo Fuel Specimens in the High Flux Isotope Reactor... Fracture Toughness Characterization of Generation II FeCrAl Alloys after ~18 dpa Irradiation Demonstration of Novel Post-Irradiation Examination Capabilities on MiniFuel Disk Specimens Microstructure Investigation and Mechanical Properties of Coated Zircaloy Cladding Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation An Atom Probe Tomography Study of the Through Wall Attenuation Effect on Cu-rich Precipitate Formation in a Reactor Pressure Vessel Steel Irradiation-induced amorphization of Fe-Y-based second phase particles in accident-tolerant FeCrAl alloys Extensive Nanoprecipitate Morphology Transformation in a Nanostructured Ferritic Alloy due to Extreme Thermomechanical Processing STEP Report on Advanced ODS FeCrAl Alloys for Fission Applications In-situ Micromechanical Testing of Neutron Irradiated FeCrAl Alloys The effect of Zr on precipitation in oxide dispersion strengthened FeCrAl alloys... Modern nanostructured ferritic alloys: A compelling and viable choice for sodium fast reactor fuel cladding applications Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys Stability of a model Fe-14Cr nanostructured ferritic alloy after long-term thermal creep Complete Status Report Documenting the Processing, Microstructure and High-Temperature Mechanical Properties of the Nanostructured Ferritic Alloy OFRAC Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration Deuterium retention in advanced steels for fusion reactor structural application Multiscale investigations of nanoprecipitate nucleation, growth, and coarsening in annealed low-Cr oxide dispersion strengthened FeCrAl powder Post irradiation examination of nanoprecipitate stability and α′ precipitation in an oxide dispersion strengthened Fe-12Cr... Pagination First page « First Previous page ‹‹ … Page 2 Current page 3 Page 4 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
