Maxim N Gussev Contact GUSSEVMN@ORNL.GOV All Publications Impact of post-irradiation annealing on mechanical performance of irradiated 718 alloy Assessing the viability of a new subsize tensile specimen geometry for evaluation of structural nuclear and additively manufactured materials A potential emerging issue concerning repair welding of out-of-core PWR components involving tritium exposure and 3He retention Microstructure, stored energy, and stability of H/He-filled nanocavities in low temperature irradiated Inconel 718 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... Mechanical Properties of Neutron-Irradiated Zr-Alloy Weldments (Batch #2) Comprehensive Characterization of Helium-Induced Degradation of the Friction Stir Weld on Neutron-Irradiated 304L Stainless Steel Microstructural Characterizations of Two High Fluence Baffle-Former Bolts Retrieved from a Westinghouse Two-loop Downflow Type PWR Microstructure and in-service degradation of baffle former bolts – in-core components of light water reactors Mechanical properties of Zircaloy cladding tubes and contributions to M.E.T.A. mechanical property database Multimodal Characterization of Stored Energy and Gas-Filled Cavities in FCC Alloys Irradiated with Spallation Neutrons and High-Energy Protons 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 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
