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Study on the Performance of Primary Means of Measurement of the Hydrogen Concentration During Severe Accidents at NPP

Atomic energy (New York, N.Y.), 2020-10, Vol.128 (6), p.333-339

2020

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The Influence of Steel Alloying on the Flow-Accelerated Corrosion of Steels in the Loops of NPPs with VVERs

Thermal engineering, 2022-08, Vol.69 (8), p.624-631

2022

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Accounting for Environmental Aspects in Water-Chemistry Optimization of the Second Loop of NPP with VVER

Atomic energy (New York, N.Y.), 2018-08, Vol.124 (4), p.255-260

2018

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Investigation of Aerosol-Deposition Induced Changes in Heat-Exchanger Material Properties During a Severe Accident at NPP

Atomic energy (New York, N.Y.), 2020-02, Vol.127 (4), p.223-227

2020

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Treatment of the Equations of Metal Oxidation Rates at Nuclear Power Plants and Thermal Power Plants in Terms of Thermodynamics

Thermal engineering, 2018-09, Vol.65 (9), p.641-650

2018

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Systematic approach to predicting corrosion of zirconium alloys in the water coolant of nuclear reactors

Atomic energy (New York, N.Y.), 2011-08, Vol.110 (4), p.265-276

2011

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Comparative tests of the efficiency of sorption-filtering materials for removing radioactive iodine from gaseous emissions

Atomic energy (New York, N.Y.), 2004-12, Vol.97 (6), p.851-857

2004

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Criteria for determining the moment of completion of the decontamination of a coolant circuit at a nuclear power station

Thermal engineering, 2006, Vol.53 (8), p.605-609

2006

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The influence of operational and water chemistry parameters on the deposits of corrosion products on fuel assemblies at nuclear power plants with VVER reactors

Thermal engineering, 2011, Vol.58 (7), p.540-546

2011

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Behavior of Radioactive Iodine Isotopes in the Multiple Forced Circulation Loop in an RBMK Reactor

Atomic energy (New York, N.Y.), 2005-08, Vol.99 (2), p.536-542

2005

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Carbon-Fiber Adsorbent Materials for Removing Radioactive Iodine from Gases

Atomic energy (New York, N.Y.), 2002-04, Vol.92 (4), p.336-340

2002

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Simulation of the behavior of activated products of corrosion during RBMK-1000 startup after scheduled major overhaul

Atomic energy (New York, N.Y.), 2001-05, Vol.90 (5), p.382-389

2001

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A method for predicting gamma-radiation dose rates in the premises of the multiple forced circulation circuit of an RBMK-1000 reactor from the data of chemical and radiospectrometric monitoring of coolant

Thermal engineering, 2009, Vol.56 (5), p.398-404

2009

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Decontamination of equipment and systems of the first unit of the Leningrad nuclear power plant when it is taken out of service

Atomic energy (New York, N.Y.), 1998-08, Vol.85 (2), p.564-568

1998

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Simulating the corrosion of zirconium alloys in the water coolant of VVER reactors

Thermal engineering, 2013, Vol.60 (7), p.457-464

2013

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The capacities of a corrosion-fatigue monitoring system in managing the service life of steam generators operating at nuclear power stations equipped with a VVER-1000M reactor

Thermal engineering, 2007-02, Vol.54 (2), p.99-103

2007

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Modeling of corrosion product migration in the secondary circuit of nuclear power plants with WWER-1200

Thermal engineering, 2016-04, Vol.63 (4), p.299-307

2016

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SYSTEMATIC APPROACH TO PREDICTING CORROSION OF ZIRCONIUM ALLOYS IN THE WATER COOLANT OF NUCLEAR REACTORS

Atomic energy (New York, N.Y.), 2011, Vol.110 (4), p.265-276

2011

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The problems of mass transfer and formation of deposits of corrosion products on fuel assemblies of a VVER-1200 reactor

Thermal engineering, 2014, Vol.61 (3), p.221-228

2014

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Analysis of the effectiveness of iodine carbon adsorbers in special ventilation systems of nuclear power plants with RBMK-1000 reactors

Atomic energy (New York, N.Y.), 1997-07, Vol.83 (1), p.520-525

1997

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Analysis of maintaining the water chemistry regimes at nuclear power stations equipped with RBMK-1000 reactors and the main lines of their improvement

Thermal engineering, 2005, Vol.52 (7), p.547-555

2005

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Some features of the effect the pH value and the physicochemical properties of boric acid have on mass transfer in a VVER reactor’s core

Thermal engineering, 2013, Vol.60 (7), p.482-486

2013

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Optimizing the water chemistry of the Novovoronezh NPP Units 3 and 4 to prevent growth of coolant pressure difference across the reactor

Thermal engineering, 2014, Vol.61 (2), p.163-171

2014

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Developing an information-analytical system for displaying and processing chemical Monitoring data for the Leningrad NPS

Thermal engineering, 2001, Vol.48 (8), p.651-656

2001

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A system of functional diagnostics and monitoring of the state of the coolant at a nuclear power station with RBMK reactors

Thermal engineering, 2000, Vol.47 (5), p.457-463

2000

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Study on the Performance of Primary Means of Measurement of the Hydrogen Concentration During Severe Accidents at NPP

The Influence of Steel Alloying on the Flow-Accelerated Corrosion of Steels in the Loops of NPPs with VVERs

Accounting for Environmental Aspects in Water-Chemistry Optimization of the Second Loop of NPP with VVER

Investigation of Aerosol-Deposition Induced Changes in Heat-Exchanger Material Properties During a Severe Accident at NPP

Treatment of the Equations of Metal Oxidation Rates at Nuclear Power Plants and Thermal Power Plants in Terms of Thermodynamics

Systematic approach to predicting corrosion of zirconium alloys in the water coolant of nuclear reactors

Comparative tests of the efficiency of sorption-filtering materials for removing radioactive iodine from gaseous emissions

Criteria for determining the moment of completion of the decontamination of a coolant circuit at a nuclear power station

The influence of operational and water chemistry parameters on the deposits of corrosion products on fuel assemblies at nuclear power plants with VVER reactors

Behavior of Radioactive Iodine Isotopes in the Multiple Forced Circulation Loop in an RBMK Reactor

Carbon-Fiber Adsorbent Materials for Removing Radioactive Iodine from Gases

Simulation of the behavior of activated products of corrosion during RBMK-1000 startup after scheduled major overhaul

A method for predicting gamma-radiation dose rates in the premises of the multiple forced circulation circuit of an RBMK-1000 reactor from the data of chemical and radiospectrometric monitoring of coolant

Decontamination of equipment and systems of the first unit of the Leningrad nuclear power plant when it is taken out of service

Simulating the corrosion of zirconium alloys in the water coolant of VVER reactors

The capacities of a corrosion-fatigue monitoring system in managing the service life of steam generators operating at nuclear power stations equipped with a VVER-1000M reactor

Modeling of corrosion product migration in the secondary circuit of nuclear power plants with WWER-1200

SYSTEMATIC APPROACH TO PREDICTING CORROSION OF ZIRCONIUM ALLOYS IN THE WATER COOLANT OF NUCLEAR REACTORS

The problems of mass transfer and formation of deposits of corrosion products on fuel assemblies of a VVER-1200 reactor

Analysis of the effectiveness of iodine carbon adsorbers in special ventilation systems of nuclear power plants with RBMK-1000 reactors

Analysis of maintaining the water chemistry regimes at nuclear power stations equipped with RBMK-1000 reactors and the main lines of their improvement

Some features of the effect the pH value and the physicochemical properties of boric acid have on mass transfer in a VVER reactor’s core

Optimizing the water chemistry of the Novovoronezh NPP Units 3 and 4 to prevent growth of coolant pressure difference across the reactor

Developing an information-analytical system for displaying and processing chemical Monitoring data for the Leningrad NPS

A system of functional diagnostics and monitoring of the state of the coolant at a nuclear power station with RBMK reactors

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