Maxim N Gussev Contact GUSSEVMN@ORNL.GOV All Publications Microstructure, deformation and fracture mechanisms in Al-4043 alloy produced by laser hot-wire additive manufacturing LWR Aging Management for Life Beyond 80 The Complexity and Challenges of Irradiation-Induced Phase Instability Phenomenon in Nuclear Power Plant Components Friction Stir Welding – an Advanced Approach to Repair Nuclear Power Plant Components On the efficacy of post-build thermomechanical treatments to improve properties of Zirconium fabricated using ultrasonic additive manufacturing Morphology and elemental composition of a new iron-rich ferrite phase in highly irradiated austenitic steel Deformation Mechanism Transition in Additively Manufactured Compositionally Graded Fe-Base Alloys... Observations of radiation-enhanced ductility in irradiated Inconel 718: Tensile properties, deformation behavior, and microst... Improved irradiation resistance of accident-tolerant high-strength FeCrAl alloys with heterogeneous structures Microstructure analysis of laser beam weldments performed on neutron-irradiated 304L steel containing 3 and 8 appm helium Burst characteristics of advanced accident-tolerant FeCrAl cladding under temperature transient testing 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 The Role of Interface in Additively Manufactured Interpenetrating Composites Ultrasonic additive manufacturing of zirconium: Pilot results Experimental Evaluation of Deformation and Fracture Mechanisms in Highly Irradiated Austenitic Steels Deformation and fracture characteristics of zirconium plate produced via ultrasonic additive manufacturing In-situ X-ray Computed Tomography Analysis of Fracture Mechanisms in Ultrasonic Additively Manufactured Al-6061 Alloy... Microstructure and mechanical performance of the Friction Stir Welds performed on neutron-irradiated steel with helium FeCrAl Accident Tolerant Fuel Cladding: Insights from a Decade of Development Complexity of deformation mechanism in neutron-irradiated 304L austenitic stainless steel at microstructural scale Mechanical Properties of Additive Manufacturing 316L Stainless Steel Before and After Neutron Irradiation - FY 2021 Quantification of in-grain lattice gradient in neutron irradiated 304L SS during deformation using insitu EBSD... Influence of neutron irradiation on Al-6061 alloy produced via ultrasonic additive manufacturing Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation Pagination First page « First Previous page ‹â¶Ä¹ Page 1 Current page 2 Page 3 … Next page ›â¶Äº Last page Last » Key Links Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Fuel Development Section Nuclear Fuel Element Performance Group
