Maxim N Gussev Contact GUSSEVMN@ORNL.GOV All Publications Assessing the viability of a new subsize tensile specimen geometry for evaluation of structural nuclear and additively manufactured materials Microstructure, stored energy, and stability of H/He-filled nanocavities in low temperature irradiated Inconel 718 A potential emerging issue concerning repair welding of out-of-core PWR components involving tritium exposure and 3He retention Complexity of segregation behavior at localized deformation sites formed while in service in a 316 stainless steel baffle-former bolt MECHANICAL BEHAVIOR OF FRESH, HYDRIDED, AND Cr-COATED CLADDING TUBES AND SUB-SIZED FLAT SPECIMENS In-service Oxidation and IASCC in High Fluence Baffle-Former Bolts Retrieved from a Westinghouse PWR... How irradiation promotes intergranular stress corrosion crack initiation Microstructure and mechanical properties of friction stir weld performed on neutron-irradiated 304L steel with helium... Recent progress in analysis of strain-induced phenomena in irradiated metallic materials and advanced alloys using SEM-EBSD in-situ tensile testing Deformation and Fracture Behavior of Additively Manufactured 316L Stainless Steel... Comprehensive Characterization of Helium-Induced Degradation of the Friction Stir Weld on Neutron-Irradiated 304L Stainless Steel Mechanical Properties of Neutron-Irradiated Zr-Alloy Weldments (Batch #2) Microstructure and in-service degradation of baffle former bolts – in-core components of light water reactors Microstructural Characterizations of Two High Fluence Baffle-Former Bolts Retrieved from a Westinghouse Two-loop Downflow Type PWR Multimodal Characterization of Stored Energy and Gas-Filled Cavities in FCC Alloys Irradiated with Spallation Neutrons and High-Energy Protons Mechanical properties of Zircaloy cladding tubes and contributions to M.E.T.A. mechanical property database Mechanical responses of 316L stainless steel printed by wire arc additive manufacturing with different thermal histories A correlation-based approach for evaluating mechanical properties of nuclear fuel cladding tubes Origin, parameters, and underlying deformation mechanisms of propagating deformation bands in irradiated 316L stainless steel Two-step deformation-induced martensitic transformation in additively manufactured High-Si stainless steel Quantifying deformation during Zry-4 burst testing: a comparison of BISON and a combined in-situ digital image correlation and infrared thermography method Micromechanical aspects of deformation and failure of advanced Iron-Chromium-Aluminum alloys Microstructure, deformation and fracture mechanisms in Al-4043 alloy produced by laser hot-wire additive manufacturing 316L Stainless Steel Wire Arc Additive Manufacturing and Characterization for Potential SNF Canister Production Friction Stir Welding – an Advanced Approach to Repair Nuclear Power Plant Components Pagination Current page 1 Page 2 Page 3 … 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
