Mikhail A Sokolov Research Staff Contact 865.574.4842 | SOKOLOVM@ORNL.GOV All Publications Effect of Creep and Oxidation on Reduced Creep-Fatigue life of Ni-based Alloy 617 at 850 ºC... Irradiation response in weldment and HIP joint of reduced activation ferritic/martensitic steel, F82H... Joining of 14YWT and F82H by Friction Stir Welding Application of Direct Current Potential Drop for Fracture Toughness Measurement... MASTER CURVE AND J-R FRACTURE TOUGHNESS OF SA508/SA533-B-1 WELD AND HAZ... Deuterium Trapping at Defects Created with Neutron- and Ion-Irradiation in Tungsten Retention of Hydrogen Isotopes in Neutron Irradiated Tungsten Low cycle fatigue and creep-fatigue behavior of Ni-based alloy 230 at 850 °C Experimental and modeling results of creep–fatigue life of Inconel 617 and Haynes 230 at 850 °C FRACTURE TOUGHNESS OF 9Cr-1MoV AND THERMALLY AGED ALLOY 617 FOR ADVANCED REACTOR APPLICATIONS Microstructure control for high strength 9Cr ferritic-martensitic steels Status and key issues of reduced activation ferritic/martensitic steels as the structural material for a DEMO blanket ... Heat Treatment Effect on Fracture Toughness of F82H Irradiated in HFIR Irradiation hardening in F82H irradiated at 573 K in the HFIR First result of deuterium retention in neutron-irradiated tungsten exposed to high flux plasma in TPE Midterm Summary of Japan-US Fusion Cooperation Program TITAN... Development of High Performance Cast Stainless Steels for ITER Shield Module... ESTIMATION OF CRACK-ARREST TOUGHNESS TRANSITION AND NDT TEMPERATURES FROM CHARPY FORCE-DISPLACEMENT IMPACT TRACES... Mechanical Properties of Neutron Irradiated Nano-structured Ferritic Alloy 14YWT Tensile and Fracture Toughness Properties of Neutron-Irradiated CuCrZr... Mechanical properties of irradiated ODS-EUROFER and nanocluster strengthened 14YWT Embrittlernent of irradiated F82H in the absence of irradiation hardening Embrittlement of Irradiated Ferritic/Martensitic Steels in the Absence of Irradiation Hardening ... Applicability of the fracture toughness master curve to irradiated highly embrittled steel and intergranular fracture... Heavy-section steel technology and irradiation programs-retrospective and prospective views Pagination First page « First Previous page ‹â¶Ä¹ … Page 2 Current page 3 Page 4 Next page ›â¶Äº Last page Last » Key Links Organizations Physical Sciences Directorate Materials Science and Technology Division Materials in Extremes Section Advanced Nuclear Materials Group
