Interpretation of Accelerated Irradiation Results for Materials of WWER-1000 Reactor Pressure Vessels

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Probabilistic analysis of mechanical properties of WWER-1000 reactor pressure vessel materials

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Determination of stress intensity factors for semielliptical surface cracks in the WWER-1000 reactor pressure vessel from the results of solving thermoelasticity boundary value problems based on the mixed mesh-projection scheme of the finite element method

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Probability Hazard Analysis of the Operation of Pipeline Systems, Tanks, and Pressure Vessels. Part 2. Method for the Evaluation of the Functional Fitness of a Structural Element According to the Restricted Statistical Data

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Prediction of Fracture Toughness of Reactor Pressure-Vessel Steels Using the “Master Curve” Concept and Probabilistic Model

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