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Assessing the durability of nuclear plant elements under high‑frequency broadband loading

Atomic energy (New York, N.Y.), 2023-05, Vol.134 (1-2), p.34-38

2023

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Development of New Construction Materials for Innovative Reactor Installation Designs

Atomic energy (New York, N.Y.), 2021-02, Vol.129 (4), p.237-241

2021

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Influence of the Edge Effect in Pipeline–Nozzle Welds During “Leak Before Break” Validation

Atomic energy (New York, N.Y.), 2022-10, Vol.132 (6), p.353-358

2022

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Welding with Pressure for Making Nuclear Reactor Components

Journal of machinery manufacture and reliability, 2023-12, Vol.52 (Suppl 1), p.S1-S5

2023

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Form Change and Cracking of RBMK-1000 Graphite Stack Blocks Under Restrained Deformation

Atomic energy (New York, N.Y.), 2021-02, Vol.129 (4), p.208-213

2021

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Computational and Experimental Validation of the Serviceability of RBMK Core Elements Under Graphite Stack Distortion Conditions

Atomic energy (New York, N.Y.), 2018-03, Vol.123 (5), p.302-306

2018

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Numerical Study of the Dynamic Strength of RBMK-1000 Stack with Fuel Channel Rupture

Atomic energy (New York, N.Y.), 2018-03, Vol.123 (5), p.349-354

2018

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Experimental Validation of the Earthquake Resistance of a Full-Scale Model of RBMK-1000 Graphite Stack with Post-Repair Characteristics

Atomic energy (New York, N.Y.), 2018-03, Vol.123 (5), p.355-357

2018

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Practical aspects of the development of a code of rules for assuring the serviceability of the elements of nuclear power facilities

Atomic energy (New York, N.Y.), 2011-05, Vol.110 (1), p.21-25

Evropin, S. V.

2011

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Stress–Strain Kinetics in Calculations of High-Temperature Strength and Longevity of Reactor Structures

Atomic energy (New York, N.Y.), 2016, Vol.119 (3), p.177-189

2016

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Service-life analysis of nuclear reactor elements under high-frequency random loading

Atomic energy (New York, N.Y.), 2013-02, Vol.113 (4), p.258-264

2013

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Specific features of elastoplastic deformation and fracture of steels at complicated thermomechanical stress paths

Inorganic materials, 2014-12, Vol.50 (15), p.1495-1505

2014

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Diagram of fatigue limit states with high asymmetry

Atomic energy (New York, N.Y.), 2013, Vol.113 (3), p.167-170

2013

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High-Temperature Heat-Treatment of the Welded Joints of Du300 Austenitic Pipelines at 900°C

Atomic energy (New York, N.Y.), 2014-10, Vol.116 (6), p.382-386

2014

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Assessing the durability of nuclear plant elements under highâfrequency broadband loading

Atomic energy (New York, N.Y.), 2023-05, Vol.134 (1-2), p.34

2023

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CONTROL OF THE SAFE OPERATING PERIOD OF EQUIPMENT AND PIPELINES IN REACTOR FACILITIES WHICH ARE IN OPERATION OR UNDER CONSTRUCTION

Atomic energy (New York, N.Y.), 2007-07, Vol.103 (1), p.560-565

2007

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Strength calculation of NPP equipment and pipelines during operation. Low- and high-cycle corrosion fatigue

The International journal of pressure vessels and piping, 2004-08, Vol.81 (8), p.719-724

2004

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Low-cycle deformation of the structures in a nuclear power plant and methods for calculating them

Atomic energy (New York, N.Y.), 2009-09, Vol.107 (3), p.173-179

2009

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Main results of life extension concept application at LNPP Unit 1

International journal of nuclear energy, science and technology, 2005, Vol.1 (4), p.274

2005

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Validation of lifetime extension of power-generating units with RBMK reactors

Atomic energy (New York, N.Y.), 2006-04, Vol.100 (4), p.310-316

2006

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Management of the Service Life of a Nuclear Power Plant

Atomic energy (New York, N.Y.), 2002-04, Vol.92 (4), p.279-286

2002

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Fourth International Scientific and Technical Conference on Innovative Projects and Technologies of Nuclear Power (MNTK NIKIET-2016)

Atomic energy (New York, N.Y.), 2017-06, Vol.122 (2), p.138-142

2017

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Creation and development of computational methods for estimating the strength of equipment and pipes used in radiochemical production processes at the industrial association mayak

Atomic energy (New York, N.Y.), 2001-09, Vol.91 (3), p.714-720

2001

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High-Temperature Heat-Treatment of the Welded Joints of Du300 Austenitic Pipelines at 900 degree C

Atomic energy (New York, N.Y.), 2014-10, Vol.116 (6), p.382-386

2014

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Reliability Computation of Heat-power Engine Structures Based on Finite Element Modeling

Safety in Technosphere, 2014-07, Vol.3 (3), p.28-36

2014

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Assessing the durability of nuclear plant elements under high‑frequency broadband loading

Development of New Construction Materials for Innovative Reactor Installation Designs

Influence of the Edge Effect in Pipeline–Nozzle Welds During “Leak Before Break” Validation

Welding with Pressure for Making Nuclear Reactor Components

Form Change and Cracking of RBMK-1000 Graphite Stack Blocks Under Restrained Deformation

Computational and Experimental Validation of the Serviceability of RBMK Core Elements Under Graphite Stack Distortion Conditions

Numerical Study of the Dynamic Strength of RBMK-1000 Stack with Fuel Channel Rupture

Experimental Validation of the Earthquake Resistance of a Full-Scale Model of RBMK-1000 Graphite Stack with Post-Repair Characteristics

Practical aspects of the development of a code of rules for assuring the serviceability of the elements of nuclear power facilities

Stress–Strain Kinetics in Calculations of High-Temperature Strength and Longevity of Reactor Structures

Service-life analysis of nuclear reactor elements under high-frequency random loading

Specific features of elastoplastic deformation and fracture of steels at complicated thermomechanical stress paths

Diagram of fatigue limit states with high asymmetry

High-Temperature Heat-Treatment of the Welded Joints of Du300 Austenitic Pipelines at 900°C

Assessing the durability of nuclear plant elements under highâfrequency broadband loading

CONTROL OF THE SAFE OPERATING PERIOD OF EQUIPMENT AND PIPELINES IN REACTOR FACILITIES WHICH ARE IN OPERATION OR UNDER CONSTRUCTION

Strength calculation of NPP equipment and pipelines during operation. Low- and high-cycle corrosion fatigue

Low-cycle deformation of the structures in a nuclear power plant and methods for calculating them

Main results of life extension concept application at LNPP Unit 1

Validation of lifetime extension of power-generating units with RBMK reactors

Management of the Service Life of a Nuclear Power Plant

Fourth International Scientific and Technical Conference on Innovative Projects and Technologies of Nuclear Power (MNTK NIKIET-2016)

Creation and development of computational methods for estimating the strength of equipment and pipes used in radiochemical production processes at the industrial association mayak

High-Temperature Heat-Treatment of the Welded Joints of Du300 Austenitic Pipelines at 900 degree C

Reliability Computation of Heat-power Engine Structures Based on Finite Element Modeling

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