TS Byun Distinguished R&D Staff and Group Leader, Radiation Effects and Microstructural Analysis Contact BYUNTS@ORNL.GOV All Publications PHASE STABILITY OF HIGHLY IRRADIATED AUSTENITIC ALLOYS DURING DEFORMATION... Fracture Behaviors of 9Cr Nanostructured Ferritic Alloy with Improved Fracture Toughness... Effects of Partial Phase Transformation on Characteristics of 9Cr Nanostructured Ferritic Alloy ... Small Specimen Reuse Technique to Evaluate Fracture Toughness of High Dose HT9 Steel ... Temperature dependence of fracture toughness in HT9 steel neutron-irradiated up to 145 dpa Investigation of temperature dependence of fracture toughness in high-dose HT9 steel using small-specimen reuse technique... Cryomilling effect on the mechanical alloying behaviour of ferritic oxide dispersion strengthened powder with Y2O3 Twinning and martensitic transformations in nickel-enriched 304 austenitic steel during tensile and indentation deformations Mechanical characteristics of SiC coating layer in TRISO fuel particles ... Post-Irradiation Fracture Toughness of Unalloyed Molybdenum, ODS molybdenum, and TZM molybdenum following irradiation at 244C... Principles and practices of irradiation creep experiment using pressurized mini-bellows... Mechanical Performance of Ferritic Martensitic Steels for High Dose Applications in Advanced Nuclear Reactors... Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part II... Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part I... Dose dependence of strength after low-temperature irradiation in metallic materials... Irradiation dose and temperature dependence of fracture toughness in high dose HT9 steel from the fuel duct of FFTF ANALYSIS OF NECKING DEFORMATION AND FRACTURE CHARACTERISTICS OF IRRADIATED A533B RPV STEEL... Analytical description of true stress-true strain curves for neutron-irradiated stainless austenitic steels... Stress relaxation behavior of nanocluster-strengthened ferritic alloy at high temperatures... Impact Properties of Irradiated HT9 from the Fuel Duct of FFTF Development of microstructure and irradiation hardening of Zircaloy during low dose neutron irradiation at nominally 358 C... Core materials development for the fuel cycle R&D program... Characterization of Mechanical Properties of Nuclear Graphite Using Subsize Specimens and Reusing Tested Specimens High Temperature Fracture Characteristics of a Nanostructured Ferritic Alloy (NFA)... Tensile fracture characteristics of nanostructured ferritic alloy 14YWT Pagination First page « First Previous page ‹‹ … Page 2 Current page 3 Page 4 … Next page ›› Last page Last » Key Links Google Scholar ORCID Organizations Physical Sciences Directorate Materials Science and Technology Division Materials in Extremes Section Radiation Effects and Microstructural Analysis Group
