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Development of Radiation Porosity in the Material of Fuel-Element Cladding Produced by Different Technologies for Fast Neutron Reactors and Its Influence on the Fuel Assembly Service Life in the BN-600 Reactor

Physics of metals and metallography, 2022-05, Vol.123 (5), p.528-534

2022

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Influence of Radiation Porosity Created in Austenitic Steel upon Neutron Irradiation on the Concentration of Intrinsic Point Defects

Physics of metals and metallography, 2020, Vol.121 (1), p.89-94

2020

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Model of the Final Stage of Nonstationary Radiation Swelling of Metals

Physics of metals and metallography, 2020-07, Vol.121 (7), p.611-617

2020

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Vacancy Migration Energy in Steels and Alloys

Physics of metals and metallography, 2019-11, Vol.120 (11), p.1133-1136

2019

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Dependence of the rate of steady-state swelling of fuel-element claddings made of ChS68 steel on the characteristics of neutron irradiation

Physics of metals and metallography, 2016-08, Vol.117 (8), p.843-846

2016

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Migration and accumulation at dislocations of transmutation helium in austenitic steels upon neutron irradiation

Physics of metals and metallography, 2016-04, Vol.117 (4), p.399-406

2016

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Effect of dose and temperature parameters of neutron irradiation to maximum damaging dose of 77 dpa on characteristics of porosity formed in steel 0.07C-16Cr-19Ni-2Mo-2Mn-Ti-Si-V-P-B

Physics of metals and metallography, 2014-06, Vol.115 (6), p.625-633

2014

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Growth in Vacancy Voids at the Initial Stage of Transient Swelling

Physics of metals and metallography, 2018-06, Vol.119 (6), p.598-605

2018

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Relation between the vacancy migration energy in austenitic steels and their resistance to irradiation-induced swelling

Russian metallurgy Metally, 2016, Vol.2016 (1), p.39-44

2016

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Research of Ti-6Al-4V titanium alloy welded joints made by electron beam welding, designed for operation in cryogenic conditions

IOP conference series. Materials Science and Engineering, 2020, Vol.971 (2), p.22005

2020

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Development of Radiation Porosity in Austenitic EK164-ID c.d. Steel Irradiated at 715–815 K to Damage Doses of 72–92 dpa

Russian metallurgy Metally, 2021-03, Vol.2021 (3), p.290-296

2021

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Vacancy Void Growth Rate as a Function of the Neutron Irradiation Parameters at the Initial Stage of Transient Swelling

Russian metallurgy Metally, 2019-03, Vol.2019 (3), p.261-267

2019

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Use of a Model for the Final Stage of Transient Swelling to Predict the Radiation-Induced Porosity in Kh18N9 Steel during Operation in the BN-600 Reactor Internals

Russian metallurgy Metally, 2020-07, Vol.2020 (7), p.799-805

2020

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Energy of vacancy migration in 0.06C-16Cr-15Ni-2Mo-2Mn-Ti-Si-V-B and 0.07C-16Cr-19Ni-2Mo-2Mn-Ti-Si-V-P-B cladding steels

Russian metallurgy Metally, 2014-05, Vol.2014 (5), p.412-418

2014

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Technology of combined chemical-mechanical fabrication of durable coatings

IOP conference series. Materials Science and Engineering, 2018-03, Vol.327 (4), p.42121

2018

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Effect of the Neutron Irradiation Characteristics on the Irradiation-Induced Swelling in a Kh18N9 Steel

Russian metallurgy Metally, 2019-07, Vol.2019 (7), p.716-720

2019

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Migration of Point Defects in the Field of a Temperature Gradient

Physics of metals and metallography, 2018-04, Vol.119 (4), p.396-401

2018

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Characteristics of radiation porosity formed upon irradiation in a BN-600 reactor in the fuel-element cans of cold-deformed steel EK-164 (06Kh16N20M2G2BTFR)-ID c.d

Physics of metals and metallography, 2012-05, Vol.113 (5), p.520-531

2012

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Characteristics of radiation porosity and structural phase state of reactor austenitic 07C–16Cr–19Ni–2Mo–2Mn–Ti–Si–V–P–B Steel after neutron irradiation at a temperature of 440–600°C to damaging doses of 36–94 dpa

Physics of metals and metallography, 2016-06, Vol.117 (6), p.611-623

2016

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Use of image-analyzing software for estimating the state of fuel elements of fast neutron reactors

Metal science and heat treatment, 2011-10, Vol.53 (7-8), p.398-402

2011

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Influence of radiation-induced voids and bubbles on physical properties of austenitic structural alloys

Journal of nuclear materials, 2004-08, Vol.329, p.617-620

2004

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Temperature effect on characteristics of void population formed in the austenitic steel under neutron irradiation up to high damage dose

Journal of nuclear materials, 2002-12, Vol.307, p.956-960

2002

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The mechanism of stress influence on swelling of 20% cold-worked 16Cr15Ni2MoTiMnSi steel

Journal of nuclear materials, 2007-08, Vol.367, p.925-929

2007

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Mechanism of the influence of transmutation helium produced in the claddings of fuel elements made of an austenitic steel ChS-68 during neutron irradiation on the formation of pores

Physics of metals and metallography, 2009-09, Vol.108 (3), p.263-269

2009

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Application of backscatter electrons for large area imaging of cavities produced by neutron irradiation

Journal of nuclear materials, 2016-11, Vol.480, p.289-300

2016

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Development of Radiation Porosity in the Material of Fuel-Element Cladding Produced by Different Technologies for Fast Neutron Reactors and Its Influence on the Fuel Assembly Service Life in the BN-600 Reactor

Influence of Radiation Porosity Created in Austenitic Steel upon Neutron Irradiation on the Concentration of Intrinsic Point Defects

Model of the Final Stage of Nonstationary Radiation Swelling of Metals

Vacancy Migration Energy in Steels and Alloys

Dependence of the rate of steady-state swelling of fuel-element claddings made of ChS68 steel on the characteristics of neutron irradiation

Migration and accumulation at dislocations of transmutation helium in austenitic steels upon neutron irradiation

Effect of dose and temperature parameters of neutron irradiation to maximum damaging dose of 77 dpa on characteristics of porosity formed in steel 0.07C-16Cr-19Ni-2Mo-2Mn-Ti-Si-V-P-B

Growth in Vacancy Voids at the Initial Stage of Transient Swelling

Relation between the vacancy migration energy in austenitic steels and their resistance to irradiation-induced swelling

Research of Ti-6Al-4V titanium alloy welded joints made by electron beam welding, designed for operation in cryogenic conditions

Development of Radiation Porosity in Austenitic EK164-ID c.d. Steel Irradiated at 715–815 K to Damage Doses of 72–92 dpa

Vacancy Void Growth Rate as a Function of the Neutron Irradiation Parameters at the Initial Stage of Transient Swelling

Use of a Model for the Final Stage of Transient Swelling to Predict the Radiation-Induced Porosity in Kh18N9 Steel during Operation in the BN-600 Reactor Internals

Energy of vacancy migration in 0.06C-16Cr-15Ni-2Mo-2Mn-Ti-Si-V-B and 0.07C-16Cr-19Ni-2Mo-2Mn-Ti-Si-V-P-B cladding steels

Technology of combined chemical-mechanical fabrication of durable coatings

Effect of the Neutron Irradiation Characteristics on the Irradiation-Induced Swelling in a Kh18N9 Steel

Migration of Point Defects in the Field of a Temperature Gradient

Characteristics of radiation porosity formed upon irradiation in a BN-600 reactor in the fuel-element cans of cold-deformed steel EK-164 (06Kh16N20M2G2BTFR)-ID c.d

Characteristics of radiation porosity and structural phase state of reactor austenitic 07C–16Cr–19Ni–2Mo–2Mn–Ti–Si–V–P–B Steel after neutron irradiation at a temperature of 440–600°C to damaging doses of 36–94 dpa

Use of image-analyzing software for estimating the state of fuel elements of fast neutron reactors

Influence of radiation-induced voids and bubbles on physical properties of austenitic structural alloys

Temperature effect on characteristics of void population formed in the austenitic steel under neutron irradiation up to high damage dose

The mechanism of stress influence on swelling of 20% cold-worked 16Cr15Ni2MoTiMnSi steel

Mechanism of the influence of transmutation helium produced in the claddings of fuel elements made of an austenitic steel ChS-68 during neutron irradiation on the formation of pores

Application of backscatter electrons for large area imaging of cavities produced by neutron irradiation

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