Maxim N Gussev Contact GUSSEVMN@ORNL.GOV All Publications Influence of hot isostatic pressing on the performance of aluminum alloy fabricated by ultrasonic additive manufacturing Influence of hot isostatic pressing on the performance of aluminum alloy fabricated by ultrasonic additive manufacturing... Accident tolerant FeCrAl fuel cladding: current status towards commercialization The Effects of Neutron Irradiation on the Mechanical Properties of Mineral Analogues of Concrete Aggregates Mechanical Behavior and Structure of Advanced Fe-Cr-Al Alloy Weldments Design, properties, and weldability of advanced oxidation resistant FeCrAl alloys ... Structure and Mechanical Properties of Improved Cast Stainless Steels for Nuclear Applications Rationalization of anisotropic mechanical properties of Al-6061 fabricated using ultrasonic additive manufacturing... Advancements in FeCrAl Alloys for Enhanced Accident Tolerant Fuel Cladding for Light Water Reactors Characterization of Materials Properties and Crack Propagation Mechanisms in Damaged Alloy 718 Leaf Springs Following Commerc... Microstructural Evolution of Type 304 and 316 Stainless Steels under Neutron Irradiation at LWR Relevant Conditions Analysis of structure and deformation behavior of AISI 316L tensile specimens from the second operational target module at the Spallation Neutron Source In-situ tube burst testing and high-temperature deformation behavior of candidate materials for accident tolerant fuel claddi... Analysis of Stress Corrosion Cracking in Alloy 718 Following Commercial Reactor Exposure Demonstration of Advanced Manufacturing Techniques for Production of Nuclear Core Structures: Ultrasonic Additive Manufacturing of Hybrid Structures Resembling HFIR Control Plates DEFORMATION LOCALIZATION AND DISLOCATION CHANNEL DYNAMICS IN NEUTRON IRRADIATED AUSTENITIC STAINLESS STEELS Deformation Behavior of Laser Welds in High Temperature Oxidation Resistant Fe-Cr-Al Alloys for Fuel Cladding Applications... Microstructural Characterization of Deformation Localization at Small Strains in a Neutron Irradiated 304 Stainless Steel ROLE OF SCALE FACTOR DURING TENSILE TESTING OF SMALL SPECIMENS... Magnetic phase formation in irradiated austenitic alloys PHASE STABILITY OF HIGHLY IRRADIATED AUSTENITIC ALLOYS DURING DEFORMATION... DEFORMATION LOCALIZATION IN HIGHLY IRRADIATED AUSTENITIC STAINLESS STEELS... Strain-induced phase transformation at the surface of an AISI-304 stainless steel irradiated to 4.4 dpa and deformed at 0.8% ... Twinning and martensitic transformations in nickel-enriched 304 austenitic steel during tensile and indentation deformations Microstructural Evolution of Type 304 Variants and 316 Stainless Steels under Neutron Irradiation Pagination First page « First Previous page ‹‹ … Page 3 Current page 4 Page 5 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
