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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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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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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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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

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

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

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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