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Scientific and technical problems of CNFC in two-component NPE and their solution in "Proryv" project

Journal of physics. Conference series, 2020-03, Vol.1475 (1), p.12001

2020

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From the First npp to Large-Scale Nuclear Power

Atomic energy (New York, N.Y.), 2014-08, Vol.116 (4), p.230-235

2014

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Analysis of Relations for Calculating Normal Heat Transfer to Supercritical Pressure Water Flow in Vertical Tubes

Atomic energy (New York, N.Y.), 2016, Vol.119 (3), p.169-176

2016

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Experimental Investigations of Heat Transfer Upon Sodium Boiling in a Model Fuel Assembly for Safety Validation of an Advanced Fast Reactor

Atomic energy (New York, N.Y.), 2016-09, Vol.120 (5), p.328-334

2016

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Modeling and comparative analysis of changeover of homogeneous and heterogeneous core of BN-1200 reactor to equilibrium mode

Nuclear engineering and design, 2022-01, Vol.386, p.111549, Article 111549

2022

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Thermal Hydraulic Studies of Liquid-Metal Coolants in Nuclear-Power Facilities

High temperature, 2018, Vol.56 (1), p.124-137

2018

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Experimental Investigations of the Characteristics of Heat-Exchange and Temperature Fields in the Channels and Fuel-Element Assemblies of Lead-Cooled Fast Reactors

Atomic energy (New York, N.Y.), 2015-09, Vol.118 (5), p.307-317

2015

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Utilization of spent nuclear fuel and transuranic actinides in a two-component nuclear power industry

Atomic energy (New York, N.Y.), 2023-05, Vol.134 (1-2), p.63-72

2023

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Analysis of the Consequences of a Large Leak in a Steam Generator in a Two-Circuit Lead-Cooled Reactor Unit

Atomic energy (New York, N.Y.), 2021-08, Vol.130 (4), p.191-196

2021

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Nuclear Power as a Component of Innovative Development in a Globalized World Economy

Atomic energy (New York, N.Y.), 2014-08, Vol.116 (4), p.236-240

2014

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Analysis and Prediction of the Physico-Mechanical Properties of Reactor Steel by Means of Artificial Intelligence and Applied Statistics

Atomic energy (New York, N.Y.), 2014-09, Vol.116 (5), p.311-314

2014

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Russian Codes for Safety Analysis of Sodium-Cooled Fast Reactors

Atomic energy (New York, N.Y.), 2014-08, Vol.116 (4), p.265-270

2014

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On the Matter of Different Approaches to a National Strategy for the Development of Nuclear Energy

Atomic energy (New York, N.Y.), 2022-07, Vol.132 (3), p.133-142

2022

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Neutron-Physical Validation of NP, AM, and CM Transmutation

Atomic energy (New York, N.Y.), 2014-09, Vol.116 (5), p.315-319

2014

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New Technological Platform for the National Nuclear Energy Strategy Development

Thermal engineering, 2017, Vol.64 (13), p.945-951

2017

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Spent Nuclear Fuel Reprocessing and Nuclear Materials Recycling in Two-Component Nuclear Energy

Atomic energy (New York, N.Y.), 2021-05, Vol.130 (1), p.29-35

2021

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Plasma separation of the elements applied to nuclear materials handling

Atomic energy (New York, N.Y.), 2006-10, Vol.101 (4), p.755-759

2006

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Computational and Experimental Validation of the Planned Emergency Heat-Removal System for BN-1200

Atomic energy (New York, N.Y.), 2014-08, Vol.116 (4), p.271-277

2014

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Thermal conductivity of lead in the temperature range of 350–1000 °C

Thermophysics and aeromechanics, 2022, Vol.29 (4), p.615-621

2022

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Correlation between the dynamic velocity and average heat transfer coefficient in transversely streamlined in-line and staggered tube bundles

Thermophysics and aeromechanics, 2020-09, Vol.27 (5), p.725-734

2020

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Analysis of the Present Status of Lead and Lead-Bismuth Coolant Technology

Atomic energy (New York, N.Y.), 2014-08, Vol.116 (4), p.285-292

2014

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Development of Fuel Pin with Uranium-Plutonium Nitride Fuel and Liquid-Metal Sublayer

Atomic energy (New York, N.Y.), 2020-03, Vol.127 (5), p.280-287

2020

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Resources and habitat conditions of the bivalve mollusk Anadara broughtonii in the northern part of Amur Bay (Sea of Japan)

Oceanology (Washington. 1965), 2012-07, Vol.52 (4), p.488-494

2012

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Studying the effective longitudinal turbulent transfer at transverse streamlining of in-line tube bundles

Thermophysics and aeromechanics, 2019-05, Vol.26 (3), p.409-415

2019

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Monitoring and control of the oxygen content in heavy liquid-metal coolants for anticorrosion protection of steels

High temperature, 2016-07, Vol.54 (4), p.564-572

2016

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Scientific and technical problems of CNFC in two-component NPE and their solution in "Proryv" project

From the First npp to Large-Scale Nuclear Power

Analysis of Relations for Calculating Normal Heat Transfer to Supercritical Pressure Water Flow in Vertical Tubes

Experimental Investigations of Heat Transfer Upon Sodium Boiling in a Model Fuel Assembly for Safety Validation of an Advanced Fast Reactor

Modeling and comparative analysis of changeover of homogeneous and heterogeneous core of BN-1200 reactor to equilibrium mode

Thermal Hydraulic Studies of Liquid-Metal Coolants in Nuclear-Power Facilities

Experimental Investigations of the Characteristics of Heat-Exchange and Temperature Fields in the Channels and Fuel-Element Assemblies of Lead-Cooled Fast Reactors

Utilization of spent nuclear fuel and transuranic actinides in a two-component nuclear power industry

Analysis of the Consequences of a Large Leak in a Steam Generator in a Two-Circuit Lead-Cooled Reactor Unit

Nuclear Power as a Component of Innovative Development in a Globalized World Economy

Analysis and Prediction of the Physico-Mechanical Properties of Reactor Steel by Means of Artificial Intelligence and Applied Statistics

Russian Codes for Safety Analysis of Sodium-Cooled Fast Reactors

On the Matter of Different Approaches to a National Strategy for the Development of Nuclear Energy

Neutron-Physical Validation of NP, AM, and CM Transmutation

New Technological Platform for the National Nuclear Energy Strategy Development

Spent Nuclear Fuel Reprocessing and Nuclear Materials Recycling in Two-Component Nuclear Energy

Plasma separation of the elements applied to nuclear materials handling

Computational and Experimental Validation of the Planned Emergency Heat-Removal System for BN-1200

Thermal conductivity of lead in the temperature range of 350–1000 °C

Correlation between the dynamic velocity and average heat transfer coefficient in transversely streamlined in-line and staggered tube bundles

Analysis of the Present Status of Lead and Lead-Bismuth Coolant Technology

Development of Fuel Pin with Uranium-Plutonium Nitride Fuel and Liquid-Metal Sublayer

Resources and habitat conditions of the bivalve mollusk Anadara broughtonii in the northern part of Amur Bay (Sea of Japan)

Studying the effective longitudinal turbulent transfer at transverse streamlining of in-line tube bundles

Monitoring and control of the oxygen content in heavy liquid-metal coolants for anticorrosion protection of steels

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