Mikhail A Sokolov Research Staff Contact 865.574.4842 | SOKOLOVM@ORNL.GOV All Publications Report on Retrieval of the Reactor Pressure Vessel A-60 Surveillance Capsule from Palisades Nuclear Generating Station MECHANICAL TEST RESULTS AND MICROSTRUCTURAL CHARACTERIZATION OF THE HARVESTED AND BASELINE ARCHIVAL ZION RPV MATERIALS Summary of LWRS Research in Addressing RPV Research Gaps in NRC EMDA Report Assessment of Different Approaches for Measuring Shear Fracture Appearance in Charpy Tests... Replacement of Hydraulic Power Units in the Fracture Mechanics Laboratory of 91°µÍø... On High-Fluence Irradiation Hardening of Nine RPV Surveillance Steels in the UCSB ATR-2 Experiment: Implications for Extended-Life Embrittlement Predictions On High-Fluence Irradiation Hardening of Nine RPV Surveillance Steels in the UCSB ATR-2 Experiment: Implications for Extended-Life Embrittlement Predictions Influence of fatigue precracking and specimen size on Master Curve fracture toughness measurements of EUROFER97 and F82H steels Specimen Size and Geometry Effects on the Master Curve Fracture Toughness Measurements of EUROFER97 and F82H Steels LWR Aging Management for Life Beyond 80 Use of Mini-CT Specimens for Fracture Toughness Characterization of Irradiated Highly Embrittled Weld Varied enhancements in mechanical properties and sodium compatibility of Grade 92 by thermomechanical treatments Fracture Toughness and Fatigue Crack Growth Rate Testing of Baffle-Former Bolts Harvested from a Westinghouse Two-Loop Downflow Type PWR Post-irradiation Examination Plan for the ORNL and University of California Santa Barbara Assessment of the UCSB ATR-2 Irradi... Technological aspects in blanket design: Effects of micro-alloying and thermo-mechanical treatments of EUROFER97 type steels after neutron irradiation An Atom Probe Tomography Study of the Through Wall Attenuation Effect on Cu-rich Precipitate Formation in a Reactor Pressure Vessel Steel Effects of HFIR neutron irradiation on fracture toughness properties of standard and Ni-doped F82H... Post-Irradiation Evaluation of Eurofer97 Fracture Toughness Using Miniature Multinotch Bend Bar Specimens Guidelines for IAEA Small Specimen Test Techniques Master Curve Fracture Toughness Testing Preliminary Plan for Evaluation of Reactor Pressure Vessel Surveillance Materials from Palisades Nuclear Generating Station Post-Irradiation Examination of High Fluence Baffle-Former Bolts Retrieved from a Westinghouse Two-Loop Downflow Type PWR Post-Irradiation Examination of High Fluence Baffle-Former Bolts Retrieved from a Westinghouse Two-Loop Downflow Type PWR Master Curve Fracture Toughness Characterization of Eurofer97 Steel Variants Using Miniature Multi-Notch Bend Bar Specimens for Fusion Applications Mechanical properties and microstructure characterization of Eurofer97 steel variants in EUROfusion program Using Automated J-R Curve Analysis Software to Simplify Testing and Save Time... Pagination Current page 1 Page 2 Page 3 … 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
