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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Computational and experimental studies of the causes of crack network formation in the area of the heat exchanger tube sheet in the BN'600 reactor von Vilenskij, O. Yu, Krylov, A.N., Osipov, S.L., Osetrov, D.L., Rogozhkin, S.A., Margolin, B.Z., Prokoshev, O.Yu, Pozdnyakov, M.L., Gulenko, A.G.

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The Comparative Analysis and Verification of the Engineering Methods for Considering the Shallow Crack Effect for the Prediction of the Fracture Toughness of the Materials for Nucl... von Kostylev, V. I., Margolin, B. Z.

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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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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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Methodical Approach to Studying Growth Kinetics for Short and Long Fatigue Cracks in Irradiated Reactor Materials: Part 1. Problem Definition. The Effect of Initial Notch Acuity on... von Smirnov, V. I., Minkin, A. J., Margolin, B. Z., Kokhonov, V. I.

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Methodical Approach to Studying Growth Kinetics for Short and Long Fatigue Cracks in Irradiated Reactor Materials: Part 2. Construction of Fatigue Propagation Rate Diagram on the B... von Smirnov, V. I., Minkin, A. J., Margolin, B. Z., Balakin, S. M.

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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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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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Further improvement of the Prometey model and Unified Curve method part 1. Improvement of the Prometey model von Margolin, B.Z., Fomenko, V.N., Gulenko, A.G., Kostylev, V.I., Shvetsova, V.A.

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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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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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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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The Basic Principles of Assessment of the Structural Integrity and Lifetime of the BN-Type Fast Neutron Reactor Components Considering Material Degradation von Margolin, B. Z., Gulenko, A. G., Buchatsky, A. A., Sorokin, A. A., Vilensky, O. Yu, Vasilev, B. A.

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Analysis of the influence of type of stress state on radiation swelling and radiation creep of austenitic steels von Margolin, B. Z., Murashova, A. I., Neustroev, V. S.

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Materials Science Aspects of Operational Safety Enhancement of Advanced VVER Based on Vessel Steel Improvements von Karzov, G. P., Margolin, B. Z., Teplukhina, I. V., Piminov, V. A.

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Special features of calculation of [C.sup.]-integral in thermomechanical loading of structural elements von Margolin, B.Z, Gulenko, A.G, Balakin, S.M

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A Physical-Mechanical Model of Ductile Fracture in Irradiated Austenitic Steels von Margolin, B. Z., Sorokin, A. A.

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