Maxim N Gussev Contact GUSSEVMN@ORNL.GOV All Publications Quantifying adherence of oxide scales on steels exposed to high temperature and pressure steam Irradiation-induced amorphization of Fe-Y-based second phase particles in accident-tolerant FeCrAl alloys Characterization of mechanical properties and deformation behavior of highly irradiated 316L stainless steel from target modules at the Spallation Neutron Source using digital image correlation analysis Mechanical Behavior of Additively Manufactured and Wrought 316L Stainless Steels Before and After Neutron Irradiation Progress Report on Plane Strain Tension Testing of ATF FeCrAl Cladding Deformation and failure of PrintCast A356/316 L composites: Digital image correlation and finite element modeling Crystallographic texture control in electron beam additive manufacturing via conductive manipulation In-situ Micromechanical Testing of Neutron Irradiated FeCrAl Alloys Mechanical Properties and Deformation Behavior of Additively Manufactured 316L Stainless Steel - FY2020 In situ measurement and modelling of the growth and length scale of twins in α-uranium Micromechanical and microstructure analysis of strain-induced phenomena in ultrasonic additively-manufactured Al-6061 alloy Influence of welding and neutron irradiation on dislocation loop formation and α′ precipitation in a FeCrAl alloy... Handbook of advanced manufactured material properties from TCR structure builds at ORNL – FY19 Length Dependence of Severe Accident Test Station Integral Testing Analysis of Localized Deformation Processes in Highly Irradiated Austenitic Stainless Steel through In Situ Techniques ASSESSMENT OF DEFORMATION MECHANISMS IN NEUTRON-IRRADIATED ACCIDENT-TOLERANT FeCrAl ALLOYS VIA IN SITU MECHANICAL TESTING AND TEM ANALYSIS FRICTION STIR WELDING AND PRELIMINARY CHARACTERIZATION OF IRRADIATED 304 STAINLESS STEEL Performance of a ferritic/martensitic steel for nuclear reactor applications fabricated using additive manufacturing Execution of Targeted Experiments to Inform BISON for ATF Materials: An Advanced Approach to Tube Burst Testing In situ SEM-EBSD analysis of plastic deformation mechanisms in neutron-irradiated austenitic steel An advanced experimental design for modified burst testing of nuclear fuel cladding materials during transient loading Beam current effect as a potential challenge in SEM-EBSD in situ tensile testing Tensile Strength and Steam Oxidation Resistance of ODS FeCrAl Sheet and Tubes Evaluation of microstructure stability at the interfaces of Al-6061 welds fabricated using ultrasonic additive manufacturing Impact of neutron irradiation on mechanical performance of FeCrAl alloy laser-beam weldments Pagination First page « First Previous page ‹‹ … Page 2 Current page 3 Page 4 … Next page ›› Last page Last » Key Links ORCID Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Fuel Development Section Nuclear Fuel Element Performance Group
