A. Sorokin

发表

Synergistic Mechanism of Radiation Embrittlement of Austenitic Stainless Steels under Long-Term High-Temperature Irradiation

V. A. Shvetsova, B. Margolin, O. Prokoshev, 2018, Inorganic Materials: Applied Research.

A Physical-Mechanical Model of Ductile Fracture in Irradiated Austenitic Steels

B. Margolin, A. Sorokin, 2013, Strength of Materials.

Embrittlement and fracture toughness of highly irradiated austenitic steels for vessel internals of WWER type reactors. Part 3. Analysis of crack propagation conditions

B. Margolin, A. Sorokin, V. Fomenko, 2010 .

Mechanisms of plastic deformation and fracture of austenitic chromium-nickel steel irradiated during 45 years in WWER-440

A. Minkin, B. Margolin, A. Sorokin, 2021, Journal of Nuclear Materials.

Investigation of irradiated metal of WWER-type reactor internals after 45 years of operation. Part 4. Mechanical properties and fracture mechanisms

V. A. Shvetsova, A. Minkin, B. Margolin, 2021 .

Physical and mechanical modeling and prediction of fracture strain and fracture toughness of irradiated austenitic steels

V. I. Smirnov, B. Margolin, A. Sorokin, 2015 .

Physical and mechanical modelling of neutron irradiation effect on ductile fracture. Part 1. Prediction of fracture strain and fracture toughness of austenitic steels

V. I. Smirnov, B. Margolin, A. Sorokin, 2014 .

Physical and mechanical modeling of the neutron irradiation effect on ductile fracture. Part 2. Prediction of swelling effect on drastic decrease in strength

B. Margolin, A. Sorokin, 2014 .

Effect of neutron irradiation on tensile properties of materials for pressure vessel internals of WWER type reactors

A. Minkin, B. Margolin, I. P. Kursevich, 2014 .

Application of the Local Approach for Prediction of Ductile Fracture of Highly Irradiated Austenitic Steels

B. Margolin, A. Sorokin, V. Kostylev, 2013 .

The radiation swelling effect on fracture properties and fracture mechanisms of irradiated austenitic steels. Part II. Fatigue crack growth rate

V. A. Shvetsova, V. I. Smirnov, A. Minkin, 2016 .

Aircraft atmospheric aerosols and ecological problems

A. Sorokin, A. V. Vatazhin, 1992 .

Correlation between grain boundary strength determined by impact test of miniature specimen and stress corrosion cracking resistance of irradiated austenitic steels used for the internals of WWER-type and PWR-type nuclear reactors

B. Margolin, A. Sorokin, N. Pirogova, 2021 .

Investigation of irradiated metal of WWER-type reactor internals after 45 years of operation. Part 3. Microstructure and phase composition

A. Minkin, B. Margolin, A. Sorokin, 2020 .

Evaluation of resistance to corrosion cracking of irradiated austenitic chromium-nickel steels by impact bending tests on miniature specimens

B. Margolin, A. Sorokin, A. Morozov, 2020 .

Investigation of high temperature annealing effectiveness for recovery of radiation-induced structural changes and properties of 18Cr–10Ni–Ti austenitic stainless steels

K. E. Prikhod’ko, B. Margolin, A. Sorokin, 2015 .

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

B. A. Gurovich, A. Minkin, B. Margolin, 2020 .

Fracture Mechanisms and Properties for Irradiated Austenitic Chromium-Nickel Steel Over Elevated Temperature Range and Formulation of Intergranular Fracture Criterion

B. Margolin, A. Sorokin, V. Shvetsova, 2023, Engineering Fracture Mechanics.

The radiation swelling effect on fracture properties and fracture mechanisms of irradiated austenitic steels. Part I. Ductility and fracture toughness

V. A. Shvetsova, V. I. Smirnov, A. Minkin, 2016 .

Laser welding of Inconel 718 nickel-based alloy layer-by-layer products

I. Logachev, A. Sorokin, A. Voropaev, 2020 .

Analysis of mechanisms inducing corrosion cracking of irradiated austenitic steels and development of a model for prediction of crack initiation

B. Margolin, A. Sorokin, A. Toivonen, 2020 .

Assessment of the crack growth rate in the material of the VVER-1000 reactor internals under irradiation creep

B. Margolin, A. Sorokin, A. Buchatsky, 2016, Inorganic Materials: Applied Research.

VERIFICATION OF THE METHODS AND SOFTWARE FOR NUMERICALLY STUDYING THE STRESSED-STRAINED STATE OF STRUCTURES MADE OF THE X16H11M3 STEEL UNDER QUASISTATIC THERMAL RADIATION LOADING

V. A. Gorokhov, V. B. Kaidalov, A. G. Gulenko, 2010 .

Turbulent air-steam jets with a condensed dispersed phase: Theory, experiment, numerical modeling

A. B. Vatazhin, Alexander Sorokin, A. Vatazhin, 1995 .

Embrittlement and fracture toughness of highly irradiated austenitic steels for vessel internals of WWER type reactors. Part 1. Relation between irradiation swelling and irradiation embrittlement. Experimental results

B. Margolin, I. P. Kursevich, A. Sorokin, 2009 .

Study of Steel Corrosion Cracking Mechanisms for VVER RPV Internals Based on Simulation Tests

M. S. Mikhailov, B. Margolin, S. N. Petrov, 2018, Inorganic Materials: Applied Research.

Features of Laser Welding Light Constructions from Cryogenic Austenitic Steel 316L

A. Sorokin, M. Kuznetsov, M. Larin, 2019, Key Engineering Materials.

Radiation-induced structure of austenitic steels with different nickel content under neutron irradiation in SM-3 and BOR-60 reactors

B. Margolin, A. Sorokin, E. Kuleshova, 2023, Voprosy Materialovedeniya.

The Relationship of Radiation Embrittlement and Swelling for Austenitic Steels for WWER Internals

B. Margolin, I. P. Kursevich, A. Sorokin, 2009 .

Mechanisms of Stress Corrosion Cracking of Irradiated Austenitic Chromium–Nickel Steels Used for WWER and PWR Vessel Internals

B. Margolin, A. Sorokin, N. Pirogova, 2021, Inorganic Materials: Applied Research.

Mechanisms of stress corrosion cracking of irradiated austenitic chromium-nickel steels used for WWER and PWR vessel internals

B. Margolin, A. Sorokin, N. Pirogova, 2020 .

Principles of alloying a novel radiation-resistant austenitic steel for the VVER-1200 reactor internals guaranteeing their safe operation for at least 60 years

B. Margolin, I. P. Kursevich, A. Sorokin, 2013, Inorganic Materials: Applied Research.

Embrittlement and fracture toughness of highly irradiated austenitic steels for vessel internals of WWER type reactors. Part 2. Relation between irradiation swelling and irradiation embrittlement. Physical and mechanical behavior

B. Margolin, I. P. Kursevich, A. Sorokin, 2010 .

Research of technological possibility of increasing erosion resistance rotor blade using laser cladding

A. Sorokin, G. Turichin, M. Kuznetsov, 2019, Procedia Manufacturing.

Investigation of Stress Corrosion Cracking Resistance of Irradiated 12Cr Ferritic-Martensitic Stainless Steel in Supercritical Water Environment

B. Margolin, A. Sorokin, N. Pirogova, 2023, Materials.

On the nature of drastic strength reduction of austenitic steels during irradiation-induced swelling

B. Margolin, A. Sorokin, 2013, Strength of Materials.

Improvement of a model to predict static fracture toughness of austenitic materials under neutron irradiation

V. I. Smirnov, B. Margolin, A. Sorokin, 2014, Inorganic Materials: Applied Research.

The Basic Principles of Assessment of the Structural Integrity and Lifetime of the BN-Type Fast Neutron Reactor Components Considering Material Degradation

B. Margolin, A. Sorokin, B. Vasilev, 2019, Inorganic Materials: Applied Research.

Basic principles for structural integrity and lifetime assessment of BN-type fast reactors components with regard for material degradation

B. A. Vasil’ev, B. Margolin, A. Sorokin, 2019, Voprosy Materialovedeniya.

Fracture strain and fracture toughness prediction for irradiated austenitic steels over wide range of temperatures taking into account the effect of swelling and thermal ageing

B. Margolin, A. Sorokin, A. V. Kozlov, 2017 .

Neutron irradiation effect on the fracture toughness of 18Cr-10Ni-Ti steel and metal of its welds

V. I. Smirnov, B. Margolin, A. Sorokin, 2012, Inorganic Materials: Applied Research.