Mikhail Sokolov

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Publications (18)

• Analysis of attenuation data from the decommissioned ZIon unit 1 reactor pressure vessel beltline weld
  Journal of Nuclear Materials 2026 DOI: 10.1016/j.jnucmat.2026.156445
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• Charpy Impact Characterization of Surveillance Specimens Harvested from Palisades High Fluence A-60 Capsule
  2025 DOI: 10.2172/3017000
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• Characterization and Quantification of Radiation-Induced Clusters/Precipitates in RPV Steels Using STEM-EDS and Machine Learning
  2025 DOI: 10.2172/3002270
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• Summary of LWRS Research in Addressing RPV Research Gaps in NRC EMDA Report
  2024 DOI: 10.2172/2483415
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• Mechanical Test Results and Microstructural Characterization of the Harvested and Baseline Archival Zion RPV Materials
  2023 DOI: 10.2172/2429857
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• Report on Retrieval of the Reactor Pressure Vessel A-60 Surveillance Capsule from Palisades Nuclear Generating Station
  2023 DOI: 10.2172/3002943
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• On High-Fluence Irradiation Hardening of Nine RPV Surveillance Steels in the UCSB ATR-2 Experiment: Implications for Extended-Life Embrittlement Predictions
  2023 DOI: 10.1520/STP164720220077
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• Replacement of Hydraulic Power Units in the Fracture Mechanics Laboratory of Oak Ridge National Laboratory
  2023 DOI: 10.2172/1988355
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• Fracture Toughness and Fatigue Crack Growth Rate Testing of Baffle-Former Bolts Harvested from a Westinghouse Two-Loop Downflow Type PWR
  2021 DOI: 10.2172/1829200
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• Post-irradiation Examination Plan for the ORNL and University of California Santa Barbara Assessment of the UCSB ATR-2 Irradiation Experiment and a Reference Document for the Irradiated Archival RPV Materials Stored in the NSUF Nuclear Fuels and Material…
  2021 DOI: 10.2172/1864444
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• Guidelines for IAEA Small Specimen Test Techniques Master Curve Fracture Toughness Testing
  2020 DOI: 10.2172/1649107
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• Preliminary Plan for Evaluation of Reactor Pressure Vessel Surveillance Materials from Palisades Nuclear Generating Station
  2020 DOI: 10.2172/1770673
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• Post-Irradiation Examination of High Fluence Baffle-Former Bolts Retrieved from a Westinghouse Two-Loop Downflow Type PWR
  2019 DOI: 10.2172/1557483
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• Fracture Toughness Characterization of Highly irradiated Reactor Pressure Weld from the ATR-2 Experiment
  2018 DOI: 10.2172/1471867
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• Mechanical properties and microstructure characterization of unirradiated Eurofer-97 steel variants for the EUROfusion project
  2018 DOI: 10.2172/1471901
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• Light Water Reactor Sustainability Program: Report on the Completion of the Machining of Zion Unit 1 Reactor Pressure Vessel Blocks into Mechanical and Microstructural Test Specimens and Chemical Analysis Coupons
  2018 DOI: 10.2172/1471907
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• Transition Fracture Toughness Characterization of Eurofer 97 Steel using Pre-Cracked Miniature Multi-notch Bend Bar Specimens
  2017 DOI: 10.2172/1414686
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• Expanded Materials Degradation Analysis (EMDA) Volume 3: Aging of Reactor Pressure Vessels
  2014 DOI: 10.2172/1513389
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