Mikhail A Sokolov Research Staff Contact sokolovm@ornl.gov | 865.574.4842 All Publications Neutron and Thermal Embrittlement of RPV Steels: An Overview... CURRENT STATUS OF THE CHARACTERIZATION OF RPV MATERIALS HARVESTED FROM THE DECOMMISSIONED ZION UNIT 1 NUCLEAR POWER PLANT... ORNL Evaluation of Safety Cases for Two Belgian Reactor Pressure Vessels Containing Quasi-Laminar Defects... USE OF MINI-CT SPECIMENS FOR FRACTURE TOUGHNESS CHARACTERIZATION OF LOW UPPER-SHELF LINDE 80 WELD ... Creep Resistance and Fracture Toughness of Recently-Developed Optimized Grade 92 and Its Weldments for Advanced Fast Reactors... The Plan for Post-Irradiation Examination of Zion Reactor Pressure Vessel Beltline Materials... Application of a Novel DCPD Adjustment Method for the J-R Curve Characterization: A study based on ORNL and ASTM Interlaborat... USE OF SMALL SPECIMENS FOR FRACTURE TOUGHNESS EVALUATION OF RPV STEELS... Influence of Processing on the Microstructure and Mechanical Properties of 14YWT... INFLUENCE OF SPECIMEN SIZE/TYPE ON THE FRACTURE TOUGHNESS OF FIVE IRRADIATED RPV MATERIALS... Friction Stir Welding of ODS and RAFM steels... Machining Test Specimens from Harvested Zion RPV Segments for Through Wall Attenuation Studies... THERMAL ANNEALING OF REACTOR PRESSURE VESSELS... MACHINING TEST SPECIMENS FROM HARVESTED ZION RPV SEGMENTS... Application of Direct Current Potential Drop for the J-integral vs. Crack Growth Resistance Curve Characterization... Evaluating the Fracture Toughness of Reactor Pressure Vessel (RPV) Materials Subject to Embrittlement... ROLE OF SCALE FACTOR DURING TENSILE TESTING OF SMALL SPECIMENS... J-R Curve Determination for Disk-shaped Compact Specimens Based on the Normalization Method and Direct Current Potential Drop... Sensitivity of ultrasonic nonlinearity to irradiated, annealed, and re-irradiated microstructure changes in RPV steels... Determining Ductile Fracture Toughness in Metals... Effect of Creep and Oxidation on Reduced Creep-Fatigue life of Ni-based Alloy 617 at 850 ºC... Expanded Materials Degradation Analysis (EMDA) Volume 3: Aging of Reactor Pressure Vessels"... 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... Pagination First page « First Previous page ‹‹ Page 1 Current page 2 Page 3 … Next page ›› Last page Last » Key Links ORCID Organizations Physical Sciences Directorate Materials Science and Technology Division Materials in Extremes Section Advanced Nuclear Materials Group