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N. V. Stepanov

Kurchatov Institute

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Application of the EBSD Method to Study the Fracture Mechanisms of Reactor Pressure Vessels Steels under Operational Factors

2021 Crystallography Reports
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Microstructure degradation of austenitic stainless steels after 45 years of operation as VVER-440 reactor internals

2020 Journal of Nuclear Materials
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Degradation of fuel rods materials based on zirconium after operation in WWER-type reactors

2019
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