Caleb Massey R&D Associate Staff Member, Advanced Fuel Fabrication and Instrumentation Contact MASSEYCP@ORNL.GOV All Publications Preliminary Report on Compositional Specification for Printed 316SS Mechanical properties of Zircaloy cladding tubes and contributions to M.E.T.A. mechanical property database 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 A correlation-based approach for evaluating mechanical properties of nuclear fuel cladding tubes The response of accident tolerant fuel cladding to LOCA burst testing: A comparative study of leading concepts Accelerated fission rate irradiation design, pre-irradiation characterization, and adaptation of conventional PIE methods for U-10Mo and U-17Mo Testing and qualification of molybdenum subcapsule welds for MiniFuel experiments... Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys Report on Evolution of Inconel 718 Following HFIR Irradiation... BISON Validation and Sensitivity Study of FeCrAl Cladding Burst during Simulated RIA Conditions On the Role of Microstructure on the Burst Properties of Oxide Dispersion Strengthened FeCrAl Alloys During Simulated Loss-of-Coolant Accident Conditions Specimen Size Artifacts Associated with a Glovebox Deployable Laser Flash Diffusivity Measurement System In situ synchrotron tensile investigations on ultrasonic additive manufactured (UAM) zirconium On the efficacy of post-build thermomechanical treatments to improve properties of Zirconium fabricated using ultrasonic additive manufacturing Hydrothermal corrosion and steam oxidation behavior comparison of UAM and conventional Zry-4 Accelerated characterization of Zircaloy-4 and ATF cladding creep behavior in accident relevant conditions Improved irradiation resistance of accident-tolerant high-strength FeCrAl alloys with heterogeneous structures BISON validation of FeCrAl cladding mechanical failure during simulated reactivity-initiated accident conditions High-Temperature Tensile and Creep Test Results on Thin Wall Tube Specimens of ODS Alloys 14YWT and OFRAC Effect of heavy ion irradiation dose rate and temperature on α′ precipitation in high purity Fe-18%Cr alloy Microchemical evolution of irradiated additive-manufactured HT9 Investigation of deformation mechanisms in an advanced FeCrAl alloy using in-situ SEM-EBSD testing Insights from microstructure and mechanical property comparisons of three pilgered ferritic ODS tubes Pagination First page « First Previous page ‹â¶Ä¹ Page 1 Current 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
