Effect of neutron irradiation on tensile properties of materials for pressure vessel internals of WWER type reactors von Sorokin, A.A., Margolin, B.Z., Kursevich, I.P., Minkin, A.J., Neustroev, V.S.

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Analysis of a link of embrittlement mechanisms and neutron flux effect as applied to reactor pressure vessel materials of WWER von Margolin, B.Z., Yurchenko, E.V., Morozov, A.M., Pirogova, N.E., Brumovsky, M.

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Mechanical Properties Degradation Modeling of Austenitic Chromium-Nickel AISI 304 Steel After Thermal Ageing von Margolin, B Z, Petrov, S N, Prokoshev, O Yu, Kondrateva, A M

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Structural Integrity Assessment and Lifetime Prediction for Inermediate Rod Bayonets Control Bayonets of Control and Protection Systems of the WWER-440 Reactor: Part 2. Structural... von Minkin, A. J., Margolin, B. Z., Fedosov, V. G.

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Investigation of high temperature annealing effectiveness for recovery of radiation-induced structural changes and properties of 18Cr–10Ni–Ti austenitic stainless steels von Gurovich, B.A., Kuleshova, E.A., Frolov, A.S., Maltsev, D.A., Prikhodko, K.E., Fedotova, S.V., Margolin, B.Z., Sorokin, A.A.

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Mechanisms of Stress Corrosion Cracking of Irradiated Austenitic Chromium–Nickel Steels Used for WWER and PWR Vessel Internals von Margolin, B. Z., Pirogova, N. E., Sorokin, A. A., Kokhonov, V. I.

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Microstructure degradation of austenitic stainless steels after 45 years of operation as VVER-440 reactor internals von Kuleshova, E.A., Fedotova, S.V., Gurovich, B.A., Frolov, A.S., Maltsev, D.A., Stepanov, N.V., Margolin, B.Z., Minkin, A.J., Sorokin, A.A.

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Structural Integrity Assessment and Lifetime Prediction for the Inermediate Rod Bayonets of Control and Protection Systems of the WWER-440 Reactor: Part 3. Optimization of Post-Irr... von Minkin, A. J., Margolin, B. Z., Belyaeva, L. A., Pirogova, N. E., Shumko, A. M., Petrov, S. N.

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Structural Integrity Assessment and Lifetime Prediction for Intermediate Control Bayonets of Control and Protection Systems (CPS) of the WWER-440 Reactor: Part 1. Investigation of... von Minkin, A. J., Margolin, B. Z., Fomenko, V. N., Belyaeva, L. A., Pirogova, N. E.

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Examination of the Irradiated Metal of WWER-Type Reactor Internals after 45 Years of Operations: Part 2. Calculation-Based and Experimental Determination of the Fluence of Fast Neu... von Pirogova, N. E., Dzhalandinov, A. D., Margolin, B. Z., Derkach, R. V., Minkin, A. J.

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Examination of the Irradiated Metal of WWER-Type Reactor Internals after 45 Years of Operations: Part 1. Research Program and Cutting out of Fragments from Pressure Vessel Internal... von Margolin, B. Z., Varovin, A. Ya, Minkin, A. J., Gurin, D. A., Glukhov, V. A.

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Prediction of the effects of thermal ageing on the embrittlement of reactor pressure vessel steels von Margolin, B.Z., Yurchenko, E.V., Morozov, A.M., Chistyakov, D.A.

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Further improvement of the Prometey model and unified curve method part 2. Improvement of the unified curve method von Margolin, B.Z., Gulenko, A.G., Fomenko, V.N., Kostylev, V.I.

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Development of Prometey local approach and analysis of physical and mechanical aspects of brittle fracture of RPV steels von Margolin, B.Z., Shvetsova, V.A., Gulenko, A.G., Kostylev, V.I.

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Embrittlement and fracture toughness of highly irradiated austenitic steels for vessel internals of WWER type reactors. Part 2. Relation between irradiation swelling and irradiatio... von Margolin, B. Z., Kursevich, I. P., Sorokin, A. A., Vasina, N. K., Neustroev, V. S.

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Prometey local approach to brittle fracture: Development and application von Margolin, B.Z., Shvetsova, V.A., Gulenko, A.G., Kostylev, V.I.

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Prediction of radiation embrittlement of WWER-1000 reactor vessel materials considering the influence of alloying elements and high content of copper von Margolin, B. Z., Yurchenko, E. V.

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Analysis of embrittlement of WWER-1000 RPV materials von Margolin, B.Z., Nikolayev, V.A., Yurchenko, E.V., Nikolayev, Yu.A., Erak, D.Yu, Nikolayeva, A.V.

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Radiation embrittlement of support structure materials for WWER RPVs von Margolin, B.Z., Yurchenko, Е.V., Kostylev, V.I., Morozov, А.М., Varovin, A.Ya, Rogozkin, S.V., Nikitin, А.А.

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Embrittlement and fracture toughness of highly irradiated austenitic steels for vessel internals of WWER type reactors. Part 1. Relation between irradiation swelling and irradiatio... von Margolin, B. Z., Kursevich, I. P., Sorokin, A. A., Lapin, A. N., Kokhonov, V. I., Neustroev, V. S.

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