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Experimental Investigations of Severe Accidents at Nuclear Power Plants

Atomic energy (New York, N.Y.), 2022-06, Vol.132 (2), p.116-123

2022

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Computational-Theoretical Investigations of Thermophysical and Physicochemical Processes Occurring During Severe Accidents at NPP–VVER

Atomic energy (New York, N.Y.), 2022-06, Vol.132 (2), p.124-128

2022

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Coolant Flow Instabilities in Power Equipment

1, 2012

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Formation of a nuclear reactor’s molten core bath in a crucible-type corium catcher for a nuclear power station equipped with VVER reactors

Thermal engineering, 2011, Vol.58 (5), p.424-428

2011

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Interaction of a material based on aluminum and iron oxides with a metal melt

Russian journal of applied chemistry, 2007-04, Vol.80 (4), p.528-535

2007

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Choice of Buffer Material for the Containment Trap for VVÉR-1000 Core Melt

Atomic energy (New York, N.Y.), 2002-01, Vol.92 (1), p.5-14

2002

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Use of refractory coatings in systems for melt containment in a serious accident at a nuclear power plant with a Vvér reactor

Atomic energy (New York, N.Y.), 2000-11, Vol.89 (5), p.868-873

2000

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Correlations for the circuit thermohydraulic codes for calculating the heat transfer crisis under boiling in rod bundles

Thermal engineering, 2003, Vol.50 (11), p.958-962

2003

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Thermal stability and catalytic properties of the composite amorphous Al2O3-nanocrystals ZrO2

Russian journal of applied chemistry, 2009-02, Vol.82 (2), p.217-221

2009

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The concept of localization of the corium melt in the ex-vessel stage of a severe accident at a nuclear power station with a VVER-1000 reactor

Thermal engineering, 2001, Vol.48 (9), p.699-706

2001

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A preliminary analysis of the simulation of processes in a NPS with VVER-640 reactors on a large-scale experimental facility

Thermal engineering, 1999, Vol.46 (3), p.185-191

1999

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Interaction between a UO2+x -ZrO2-Fe(Cr, Ni)Oy melt and a concrete based on ZrO2

Refractories and industrial ceramics, 2000-01, Vol.41 (1), p.19-23

2000

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Phase relations in the ZrO2-FeO system

Russian journal of inorganic chemistry, 2006-02, Vol.51 (2), p.325-331

2006

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Analyzing the possibility of retaining the corium in the vessel of a VVER-640 reactor in a severe accident with a damaged core

Thermal engineering, 1996, Vol.43 (11), p.888-892

1996

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The interaction of nuclear reactor core melt with oxide sacrificial material of localization device for a nuclear power plant with water-moderated water-cooled power reactor

High temperature, 2007-02, Vol.45 (1), p.22-31

2007

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Phase and chemical transformations in the SiO2-Fe2O3(Fe3O4) system at various oxygen partial pressures

Russian journal of inorganic chemistry, 2006-01, Vol.51 (1), p.118-125

2006

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Phase transformation in the binary section of the UO2-FeO-Fe system

Radiochemistry (New York, N.Y.), 2007-02, Vol.49 (1), p.20-24

2007

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The specifics of crisis phenomena in steam-generating channels for low parameters of the coolant

Thermal engineering, 1999, Vol.46 (3), p.208-215

1999

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Pressure drop oscillation under conditions of thermal and hydraulic instability of two-phase flow

High temperature, 1993, Vol.31 (5), p.697-703

KHABENSKII, V. B

1993

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Experimental study of the thermal and hydraulic characteristics of heat-transfer surfaces formed by spherical cavities

High temperature, 1991-11, Vol.29 (6), p.928-932

1991

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Sacrificial materials for safety systems of nuclear power stations : A new class of functional materials

Thermal engineering, 2001, Vol.48 (9), p.721-724

2001

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The device for core melt localization at the Tyan'van Nuclear Power Station with a VVER-1000 reactor

Thermal engineering, 2001, Vol.48 (9), p.707-712

2001

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Choice of buffer material for the containment trap for vvér-1000 core melt

Atomic energy (New York, N.Y.), 2002, Vol.92 (1), p.5-14

2002

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Experimental investigation of processes arising when flooding a steel melt

Thermal engineering, 2001, Vol.48 (9), p.725-731

2001

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Interaction between a UO2+x - ZrO2 - Fe(Cr, Ni)Oy melt and a concrete based on ZrO2

Refractories and industrial ceramics, 2000, Vol.41 (1-2), p.19-23

2000

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Experimental Investigations of Severe Accidents at Nuclear Power Plants

Computational-Theoretical Investigations of Thermophysical and Physicochemical Processes Occurring During Severe Accidents at NPP–VVER

Coolant Flow Instabilities in Power Equipment

Formation of a nuclear reactor’s molten core bath in a crucible-type corium catcher for a nuclear power station equipped with VVER reactors

Interaction of a material based on aluminum and iron oxides with a metal melt

Choice of Buffer Material for the Containment Trap for VVÉR-1000 Core Melt

Use of refractory coatings in systems for melt containment in a serious accident at a nuclear power plant with a Vvér reactor

Correlations for the circuit thermohydraulic codes for calculating the heat transfer crisis under boiling in rod bundles

Thermal stability and catalytic properties of the composite amorphous Al2O3-nanocrystals ZrO2

The concept of localization of the corium melt in the ex-vessel stage of a severe accident at a nuclear power station with a VVER-1000 reactor

A preliminary analysis of the simulation of processes in a NPS with VVER-640 reactors on a large-scale experimental facility

Interaction between a UO2+x -ZrO2-Fe(Cr, Ni)Oy melt and a concrete based on ZrO2

Phase relations in the ZrO2-FeO system

Analyzing the possibility of retaining the corium in the vessel of a VVER-640 reactor in a severe accident with a damaged core

The interaction of nuclear reactor core melt with oxide sacrificial material of localization device for a nuclear power plant with water-moderated water-cooled power reactor

Phase and chemical transformations in the SiO2-Fe2O3(Fe3O4) system at various oxygen partial pressures

Phase transformation in the binary section of the UO2-FeO-Fe system

The specifics of crisis phenomena in steam-generating channels for low parameters of the coolant

Pressure drop oscillation under conditions of thermal and hydraulic instability of two-phase flow

Experimental study of the thermal and hydraulic characteristics of heat-transfer surfaces formed by spherical cavities

Sacrificial materials for safety systems of nuclear power stations : A new class of functional materials

The device for core melt localization at the Tyan'van Nuclear Power Station with a VVER-1000 reactor

Choice of buffer material for the containment trap for vvér-1000 core melt

Experimental investigation of processes arising when flooding a steel melt

Interaction between a UO2+x - ZrO2 - Fe(Cr, Ni)Oy melt and a concrete based on ZrO2

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