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Evolution of the nanostructure of VVER-1000 RPV materials under neutron irradiation and post irradiation annealing

Journal of nuclear materials, 2009-04, Vol.385 (3), p.615-622

2009

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Grain Refinement of the HAZ Metal due to Welding

Physics of atomic nuclei, 2023-12, Vol.86 (8), p.1921-1927

2023

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Determination of Energy Release from Gamma Radiation in Experimental Channels of the IR-8 Reactor

Physics of atomic nuclei, 2023-12, Vol.86 (8), p.1768-1777

2023

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Studying Metal of Nozzles of VVER-440 Pressure Vessel after 45 Years of Operation

Inorganic materials : applied research, 2021-11, Vol.12 (6), p.1695-1700

2021

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Influence of Certain Metallurgical Factors on the Lifetime of Weld Joints of Metal of VVER-1000 and VVER-1200 Reactor Vessels

Physics of atomic nuclei, 2022-12, Vol.85 (8), p.1323-1334

2022

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Computational and Experimental Method for Determination of the Inertia of Thermocouples within the Framework of Pre-Reactor Tests of Experimental Fuel Rods

Physics of atomic nuclei, 2023-12, Vol.86 (12), p.2577-2584

2023

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Evolution of microstructure and mechanical properties of VVER-1000 RPV steels under re-irradiation

Journal of nuclear materials, 2015-01, Vol.456, p.373-381

2015

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Evolution of structure and properties of VVER-1000 RPV steels under accelerated irradiation up to beyond design fluences

Journal of nuclear materials, 2015-01, Vol.456, p.23-32

2015

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Analysis of Mechanical Properties and Nanostructure Changes of VVER-440 Reactor Pressure Vessel Metal after Annealing

Physics of atomic nuclei, 2021-12, Vol.84 (10), p.1676-1690

2021

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Phase and structural transformations in VVER-440 RPV base metal after long-term operation and recovery annealing

Journal of nuclear materials, 2018-04, Vol.501, p.261-274

2018

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Study of the Unirradiated Weld Metal of the VVER-440 Reactor Vessel after 45 Years of Operation

Inorganic materials : applied research, 2022-12, Vol.13 (6), p.1727-1735

2022

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Effect of the Operation Factors on the Properties of the Heat Affected Zone in VVER-1000 RPV according to the Results of Surveillance Specimens

Russian metallurgy Metally, 2021-10, Vol.2021 (10), p.1356-1362

2021

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Irradiation temperature, flux and spectrum effects

Progress in nuclear energy (New series), 2011-08, Vol.53 (6), p.756-759

2011

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Study of nozzles' metal of VVER-440 pressure vessel after 45 years of exploitation

Voprosy Materialovedeniya, 2021-02 (4(104)), p.192-199

2021

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Validation of 3D Code KATRIN For Fast Neutron Fluence Calculation of VVER-1000 Reactor Pressure Vessel by Ex-Vessel Measurements and Surveillance Specimens Results

EPJ Web of Conferences, 2016, Vol.106, p.3011

2016

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Investigation of the Microstructure Factors Affecting the Brittle Fracture Initiation of Pre-Cracked Charpy-Type Samples of VVER-1000 RPV Steel

Key engineering materials, 2014-01, Vol.592-593, p.635-638

2014

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Degradation of RPV steel structure after 45 years of operation in the VVER-440 reactor

Journal of nuclear materials, 2020-11, Vol.540, p.152362, Article 152362

2020

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Nature of defect clusters in neutron-irradiated iron-based alloys deduced from small-angle neutron scattering

Journal of nuclear materials, 2008-02, Vol.373 (1), p.199-205

2008

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Study of PRIMAVERA steel samples by a positron annihilation spectroscopy technique

Journal of nuclear materials, 2010-11, Vol.406 (2), p.257-262

2010

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Correlation of local parameters of brittle crack initiation and propagation with the fracture toughness of VVER-1000 pressure vessel steels

Engineering fracture mechanics, 2018-10, Vol.202, p.162-173

2018

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Interpretation of Accelerated Irradiation Results for Materials of WWER-1000 Reactor Pressure Vessels

Strength of materials, 2013-07, Vol.45 (4), p.424-432

2013

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Prediction of radiation embrittlement of VVER-1000 RPV welded seam material at lifetime extension up to 60 years and more

Voprosy Materialovedeniya, 2024-02 (4(116)), p.227-244

2024

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Comparison of microstructural features of radiation embrittlement of VVER-440 and VVER-1000 reactor pressure vessel steels

Journal of nuclear materials, 2002-02, Vol.300 (2), p.127-140

2002

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Evaluation of the Radiation Resistance and Thermal Stability of 15KH2MFA-A, Modifications a and B, Steel and Weld-Seam Metal

Atomic energy (New York, N.Y.), 2014-10, Vol.116 (6), p.373-381

2014

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Modernization of Existing VVER-1000 Surveillance Programs

Journal of ASTM International, 2012-04, Vol.9 (4), p.1-10

2012

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Evolution of the nanostructure of VVER-1000 RPV materials under neutron irradiation and post irradiation annealing

Grain Refinement of the HAZ Metal due to Welding

Determination of Energy Release from Gamma Radiation in Experimental Channels of the IR-8 Reactor

Studying Metal of Nozzles of VVER-440 Pressure Vessel after 45 Years of Operation

Influence of Certain Metallurgical Factors on the Lifetime of Weld Joints of Metal of VVER-1000 and VVER-1200 Reactor Vessels

Computational and Experimental Method for Determination of the Inertia of Thermocouples within the Framework of Pre-Reactor Tests of Experimental Fuel Rods

Evolution of microstructure and mechanical properties of VVER-1000 RPV steels under re-irradiation

Evolution of structure and properties of VVER-1000 RPV steels under accelerated irradiation up to beyond design fluences

Analysis of Mechanical Properties and Nanostructure Changes of VVER-440 Reactor Pressure Vessel Metal after Annealing

Phase and structural transformations in VVER-440 RPV base metal after long-term operation and recovery annealing

Study of the Unirradiated Weld Metal of the VVER-440 Reactor Vessel after 45 Years of Operation

Effect of the Operation Factors on the Properties of the Heat Affected Zone in VVER-1000 RPV according to the Results of Surveillance Specimens

Irradiation temperature, flux and spectrum effects

Study of nozzles' metal of VVER-440 pressure vessel after 45 years of exploitation

Validation of 3D Code KATRIN For Fast Neutron Fluence Calculation of VVER-1000 Reactor Pressure Vessel by Ex-Vessel Measurements and Surveillance Specimens Results

Investigation of the Microstructure Factors Affecting the Brittle Fracture Initiation of Pre-Cracked Charpy-Type Samples of VVER-1000 RPV Steel

Degradation of RPV steel structure after 45 years of operation in the VVER-440 reactor

Nature of defect clusters in neutron-irradiated iron-based alloys deduced from small-angle neutron scattering

Study of PRIMAVERA steel samples by a positron annihilation spectroscopy technique

Correlation of local parameters of brittle crack initiation and propagation with the fracture toughness of VVER-1000 pressure vessel steels

Interpretation of Accelerated Irradiation Results for Materials of WWER-1000 Reactor Pressure Vessels

Prediction of radiation embrittlement of VVER-1000 RPV welded seam material at lifetime extension up to 60 years and more

Comparison of microstructural features of radiation embrittlement of VVER-440 and VVER-1000 reactor pressure vessel steels

Evaluation of the Radiation Resistance and Thermal Stability of 15KH2MFA-A, Modifications a and B, Steel and Weld-Seam Metal

Modernization of Existing VVER-1000 Surveillance Programs

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