TS Byun Distinguished R&D Staff and Group Leader, Radiation Effects and Microstructural Analysis Contact byunts@ornl.gov | 865.341.0391 All Publications 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... Feasibility Studies and Downselection of New Materials and Manufacturing Technologies for Nuclear Applications Oak Ridge National Laboratory Compilation of AMMT Quality Assurance Procedures Progress on Producing an ODS Ferritic Alloy by High Deformation Processing of Reactive Powders AMMT FY23 HFIR Irradiation Test Matrix – Supported by the Design of a Miniature Bend Bar Irradiation Vehicle Downselection and Basic Properties of Additively Manufactured ODS Alloys Role of geometric dynamic recrystallization in nanocrystalline alloys Mechanical Properties of Additively Manufactured 316L Stainless Steel Before and After Neutron Irradiation–FY23 Metal forming and working of stabilized nanocrystalline Cu-Ta for electrical contacts... Detecting Thermally-Induced Spinodal Decomposition with Picosecond Ultrasonics in Cast Austenitic Stainless Steels... Two-step deformation-induced martensitic transformation in additively manufactured High-Si stainless steel Deformation Mechanism Transition in Additively Manufactured Compositionally Graded Fe-Base Alloys... Characterization of radiation damage in 3D printed SiC A comprehensive study of the effects of long-term thermal aging on the fracture resistance of cast austenitic stainless steel... Irradiation hardening and ductility loss of Eurofer97 steel variants after neutron irradiation to ITER-TBM relevant condition... Evolution of the role of molybdenum in duplex stainless steels during thermal aging: From enhancing spinodal decomposition to... Mechanical Properties of Additive Manufacturing 316L Stainless Steel Before and After Neutron Irradiation - FY 2021 Current Status of HFIR Irradiation Testing Supporting the Transformational Challenge Reactor... Mechanical and Thermophysical Properties of 3D-Printed SiC before and after Neutron Irradiation – FY 2021... Irradiation stability and thermomechanical properties of 3D-printed SiC... Correlative STEM-APT characterization of radiation-induced segregation and precipitation of in-service BWR 304 stainless stee... Creep Behavior of 316L Stainless Steel Manufactured by Laser Powder Bed Fusion... Mechanical Behavior of Additively Manufactured and Wrought 316L Stainless Steels Before and After Neutron Irradiation Degradation of impact toughness in cast stainless steels during long-term thermal aging... Pagination Current page 1 Page 2 Page 3 … Next page ›› Last page Last » Key Links Google Scholar ORCID