Maxim N Gussev Contact gussevmn@ornl.gov | 865.574.4456 All Publications 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 I... Design and Analysis of an Advanced Three-Point Bend Test Approach for Miniature Irradiated Disk Specimens... Performance of FeCrAl Accident Tolerant Fuel Cladding under Reactivity Insertion Accident Condition Testing... Characterization of mechanical properties and deformation behavior of highly irradiated 316L stainless steel from target modu... 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... 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... Pagination First page « First Previous page ‹‹ Page 1 Current 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