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Software model in nuclear power design and control

Journal of physics. Conference series, 2020, Vol.1679 (3), p.32027

2020

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Methodology of Analysis of Thermal Vision Parameters of NPP Standby Diesel Generators Together with Standard Instrument Readings

Physics of atomic nuclei, 2023-12, Vol.86 (11), p.2384-2391

2023

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Operational Experience of Stationary Technical Diagnostics Systems at Novovoronezh NPP

Глобальная ядерная безопасность, 2022-08 (4), p.36-46

2022

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Diagnostics of the drive of the control and protection system of the reactor plant ark type

Глобальная ядерная безопасность, 2023-06 (2), p.79-87

2023

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Evaluation of the Effect of Thermal Stratification on the Residual Life of the Surge Line of the Pressure Compensator in the No. 5 Unit of the Novovoronezh NPP

Atomic energy (New York, N.Y.), 2016-05, Vol.120 (1), p.22-28

Povarov, V. P.

2016

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Concept of Creating an Integrated Automated Thermal Imaging Control System

Глобальная ядерная безопасность, 2022-08 (1), p.60-66

2022

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VVER-1200 Tests in No. 6 Unit of the Novovoronezh NPP During Operation in a Daily Load Schedule

Atomic energy (New York, N.Y.), 2021-01, Vol.129 (3), p.113-121

2021

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Analysis of the Reasons for Damage in the Welded Assembly Joining the Hot Collector of First-Loop Coolant to the Du 1200 Tube of the Steam Generators in No. 5 Unit of the Novovoronezh NPP

Atomic energy (New York, N.Y.), 2016, Vol.119 (3), p.153-162

2016

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Investigation of Transient Xenon Processes in VVER-1200 at the Novovoronezh NPP

Atomic energy (New York, N.Y.), 2018-08, Vol.124 (4), p.215-220

2018

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Restoration of metal properties of circulation pump blades by the method of surface ultrasonic impact treatment

Thermal engineering, 2017, Vol.64 (10), p.762-769

2017

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Monitoring the Condition of Safety Barriers in Nuclear Power Plants

Atomic energy (New York, N.Y.), 2015-06, Vol.118 (2), p.79-84

2015

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Engineering the functions and performance requirements for the “Virtual Operator” functional group control digital system

AIP Conference Proceedings, 2021, Vol.2402 (1)

2021

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New data transfer and display system development for NPP safety

Глобальная ядерная безопасность, 2024-09 (3), p.27-34

2024

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Modernisation of rotor hydraulic lift pump of steam turbine unit K-1200-6.8/50

Глобальная ядерная безопасность, 2024-09 (3), p.56-61

2024

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Methods and means of ensuring the accuracy of bending deformation measurements of connecting pipe between the VVER reactor and the steam generator in the conditions of a fuel campaign

Глобальная ядерная безопасность, 2024-06 (2), p.61-72

2024

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Some aspects of the re-extension of the reactor plant life with VVER-440 on the example of Novovoronezh NPP UNIT 4

Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika, 2019-06, Vol.2019 (2), p.91-104

2019

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Investigation of VVÉR-1000 Behavior in a Transient Process Caused by a Small Power Decrease

Atomic energy (New York, N.Y.), 2002-10, Vol.93 (4), p.853-854

2002

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Using the Offset-Power Diagram to Monitor the Local Linear Power Density of Fuel Elements in a VVÉR-1000 Core

Atomic energy (New York, N.Y.), 2002-07, Vol.93 (1), p.547-553

2002

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The effect of the position of the ionization chambers relative to the individual control elements of a VVER-1000 reactor on the readings of the reactivity meters

Thermal engineering, 2003, Vol.50 (5), p.372-375

2003

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Improving the transient stability of VVER-1000 reactor-based nuclear power plant units

Thermal engineering, 2014, Vol.61 (1), p.47-53

2014

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An analysis of factors causing the occurrence of off-design thermally induced force effects in the zone of weld joint no. 111-1 in a PGV-1000M steam generator and recommendations on excluding them

Thermal engineering, 2014-08, Vol.61 (8), p.541-550

2014

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Erratum to: “Development and application of an information–analytic system on the problem of flow accelerated corrosion of pipeline elements in the secondary coolant circuit of VVER-440-based power units at the Novovoronezh Nuclear Power Plant”

Thermal engineering, 2016-07, Vol.63 (7), p.527-527

2016

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Optimized planning of in-service inspections of local flow-accelerated corrosion of pipeline elements used in the secondary coolant circuit of the VVER-440-based units at the Novovoronezh NPP

Thermal engineering, 2015, Vol.62 (3), p.227-232

2015

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Development and application of an information-analytic system on the problem of flow accelerated corrosion of pipeline elements in the secondary coolant circuit of VVER-440-based power units at the Novovoronezh nuclear power plant

Thermal engineering, 2015-02, Vol.62 (2), p.138-145

2015

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Development of a specialized measuring complex and experience with its operation in starting power unit no. 1 at the Rostov NPS

Thermal engineering, 2003, Vol.50 (5), p.369-371

2003

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Software model in nuclear power design and control

Methodology of Analysis of Thermal Vision Parameters of NPP Standby Diesel Generators Together with Standard Instrument Readings

Operational Experience of Stationary Technical Diagnostics Systems at Novovoronezh NPP

Diagnostics of the drive of the control and protection system of the reactor plant ark type

Evaluation of the Effect of Thermal Stratification on the Residual Life of the Surge Line of the Pressure Compensator in the No. 5 Unit of the Novovoronezh NPP

Concept of Creating an Integrated Automated Thermal Imaging Control System

VVER-1200 Tests in No. 6 Unit of the Novovoronezh NPP During Operation in a Daily Load Schedule

Analysis of the Reasons for Damage in the Welded Assembly Joining the Hot Collector of First-Loop Coolant to the Du 1200 Tube of the Steam Generators in No. 5 Unit of the Novovoronezh NPP

Investigation of Transient Xenon Processes in VVER-1200 at the Novovoronezh NPP

Restoration of metal properties of circulation pump blades by the method of surface ultrasonic impact treatment

Monitoring the Condition of Safety Barriers in Nuclear Power Plants

Engineering the functions and performance requirements for the “Virtual Operator” functional group control digital system

New data transfer and display system development for NPP safety

Modernisation of rotor hydraulic lift pump of steam turbine unit K-1200-6.8/50

Methods and means of ensuring the accuracy of bending deformation measurements of connecting pipe between the VVER reactor and the steam generator in the conditions of a fuel campaign

Some aspects of the re-extension of the reactor plant life with VVER-440 on the example of Novovoronezh NPP UNIT 4

Investigation of VVÉR-1000 Behavior in a Transient Process Caused by a Small Power Decrease

Using the Offset-Power Diagram to Monitor the Local Linear Power Density of Fuel Elements in a VVÉR-1000 Core

The effect of the position of the ionization chambers relative to the individual control elements of a VVER-1000 reactor on the readings of the reactivity meters

Improving the transient stability of VVER-1000 reactor-based nuclear power plant units

An analysis of factors causing the occurrence of off-design thermally induced force effects in the zone of weld joint no. 111-1 in a PGV-1000M steam generator and recommendations on excluding them

Erratum to: “Development and application of an information–analytic system on the problem of flow accelerated corrosion of pipeline elements in the secondary coolant circuit of VVER-440-based power units at the Novovoronezh Nuclear Power Plant”

Optimized planning of in-service inspections of local flow-accelerated corrosion of pipeline elements used in the secondary coolant circuit of the VVER-440-based units at the Novovoronezh NPP

Development and application of an information-analytic system on the problem of flow accelerated corrosion of pipeline elements in the secondary coolant circuit of VVER-440-based power units at the Novovoronezh nuclear power plant

Development of a specialized measuring complex and experience with its operation in starting power unit no. 1 at the Rostov NPS

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