ATOMIC ENERGY

Radioactivity Monitoring of the Surface Air Layer and Atmospheric Fallout Near NPP

Radiolysis of 232,234 U-Enriched Regenerated-Uranium Hexafluoride at the Temporary Storage Stage in a Separation Plant

Method of Solving Problems of Two-Phase Heat- and Hydrodynamics with Sodium Coolant

Results of Studies and Life Tests of Russian-Made Monodisperse Nuclear-Grade Ion-Exchange Resins

Neutronics Model of the IVG.1M Reactor: Development and Critical-State Verification

On a Strategy for the Development of Nuclear Power in Russia

Coolant Mixing Intensity and Hydraulic Resistance of FA Mixing Grids

Conceptual Design of Small NPP with RITM-200 Reactor

Characteristics of Heat Transfer During Boiling of Liquid Metal in the Fuel Assemblies of Fast Reactors in Emergency Regimes

LiF–NaF–KF Eutectic Based Fast Molten-Salt Reactor as Np, Am, Cm Transmuter

Volume-Localized Quantum Levels in Charged Fullerenes

Partial Equations of Reactor Kinetics

Energy Efficiency Enhancement of Ionic Diode for Neutron Generation with Electronic Conduction Suppression by the Field of a Permanent Magnet

Experimental Thermophysical Studies in Validation of the Operability of Passive Safety Systems for Next-Generation VVER

Solidification of Spent Ion-Exchange Resin Pulps with Aid of Polymer Binders

Working Liquid Holdup by Irregular Fine Packing in Uranium Hexafluoride Rectification

Investigation of the Amplitude-Time Characteristics of a Penning Discharge in Miniature Ion Sources

Control Features of the Useful Capacity of Reactor Units with a Gas-Turbine Cycle

Power Schedule Optimization of the PIK Reactor to Accelerate Power Buildup During Startup

Investigation of PuF 3 and AmF 3 Solubility in 73LiF–27BeF 2 Melt

Corrosion Resistance of Experimental Fuel-Rod Cladding Tested in a Materials Science Research Reactor Under PWR Conditions

Method of Performing Uncertainty Analysis Using Neutron Covariance Data for HTGR

Calculation of the Neutron Distribution Function in Slabs with Extended Heterogeneous Fuel Zones

Reactivity Determination with One Neutron Detector in a Transport-PWR Core

Critical Heat Flux During Boiling in Channels and Rod Assemblies: Problems of Data Description and Generalization

Computational Modeling of Systems with Low Heat Fluxes

Theoretical Basis for Using Hydrogen Reduction in Titanium Production

Determination of the Core Power of a Critical Assembly by Different Methods

Assessment of the Safe Isolation of Solid Radwaste in Subsurface Repositories

Key Results of Computational and Experimental Studies of Passive Systems of Emergency Heat Removal

Prospective Micro-Encapsulated Fuel with Silicon Carbide Protective Coat

Rehabilitation of Building 53 at VNIINM

Digital Decommissioning Software-Hardware Package – Tool for Design and Management of the Decommissioning of Nuclear Facilities

Investigation of the Character of Stored-Energy Release from Graphite Irradiated at High Temperature

Investigation of Americium Sorption from Model Liquid Radwaste Solutions Using TODGA-Based Solid-Phase Extractant

Transverse Transport and Heat Transfer in Smooth VVER Fuel-Rod Bundle with Cellular Spacer Grid

Forecast of the Radioecological Consequences of Hypothetical Accidents in Nuclear and Radiation Hazardous Objects Located at the Bottom of the Barents and Kara Seas

Impact of Deferred SNF Financial Liabilities on NFC Backend Strategy

Small Nuclear Power Plants – Primary Avenue for Reducing Risks and their Consequences in Nuclear Power

Few-Group Library of Neutronic Constants for Fast Calculations

Tritium in Nitride Fuel of Fast Reactors

Results of Studies of BN-600 Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel and ChS68-ID c.d. Steel Cladding

Calculation of the Dose Distribution Near the Gantry of a Radiotherapy System

Concept Selection and Neutronic Characteristics of Nuclear Icebreaker Cores

Radioecological Studies in the Murmansk Littoral of the Barents Sea as Part of Environmental Monitoring in Radwaste Management

Corrosion Damage and Mechanical Properties of BR-10 Reactor Fuel-Rod Cladding with Mononitride Uranium Fuel

Basic Concepts of a Modular Fast Sodium Reactor with Metallic Fuel