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Embrittlement mechanisms and magnetic properties optimization conditions in amorphous Co69Ge3.7Cr3.8Si12.5B11 alloy without ductile-brittle transition
Kekalo I.B., Mogilnikov P.S.
The Basic Principles of Assessment of the Structural Integrity and Lifetime of the BN-Type Fast Neutron Reactor Components Considering Material Degradation
Margolin B.Z., Gulenko A.G., Buchatsky A.A., Sorokin A.A., Vilensky O.Y., Vasilev B.A.
Effect of power pulses of deuterium plasma on the structure and mechanical properties of chromium steel
Tsepelev A.B., Ilyushin A.S., Kiseleva T.Y., Brovkina E.A., Vinogradova N.A.
Influence of Neutron Irradiation and Post-Irradiation Annealing on Mechanical Properties and Fracture Toughness of Anticorrosive Cladding for VVER-Type Reactors: Part 2. Predictive Modeling of the Mechanical Properties and Fracture Toughness of Cladding
Margolin B.Z., Kostylev V.I., Morozov A.M., Varovin A.Y., Belyaeva L.A., Potapova V.A., Smirnov V.I., Prokoshev O.Y., Petrov S.N.
Influence of Neutron Irradiation and Post-Irradiation Annealing on Mechanical Properties and Fracture Toughness of the Anticorrosive Cladding for VVER-Type Reactors: Part 1. Mechanisms of Embrittlement and Recovery of Cladding Properties
Margolin B.Z., Morozov A.M., Varovin A.Y., Kostylev V.I., Belyaeva L.A., Potapova V.A., Smirnov V.I., Prokoshev O.Y., Petrov S.N.
Synergistic Mechanism of Radiation Embrittlement of Austenitic Stainless Steels under Long-Term High-Temperature Irradiation
Shvetsova V.A., Prokoshev O.Y., Margolin B.Z., Sorokin A.A., Potapova V.A.
Prediction of radiation embrittlement of WWER-1000 reactor vessel materials considering the influence of alloying elements and high content of copper
Margolin B.Z., Yurchenko E.V.
Some problems of hydrogen in reactor structural materials: A review
Chernov I.I., Staltsov M.S., Kalin B.A., Guseva L.Y.
Influence of hydrogen embrittlement on the localization of plastic strain in Al–Cu–Mg alloy
Barannikova S.A., Bochkareva A.V., Lunev A.G., Gorbatenko V.V., Zuev L.B.
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