Atomic Energy

Article	Citations
Nuclear-Magnetic Flowmeter-Relaxometers for Monitoring Coolant and Feedwater Flow and Status in Npp	46
The World’s First Floating NPP: Origination and Direction of Future Development	11
Optimization of a Square Cascade of Centrifuges for Separation of Multicomponent Mixtures of Stable Isotopes	10
Brest Lead-Cooled Fast Reactor: From Concept to Technological Implementation	10
Molybdenum Isotope Separation in a Cascade with a Specified Number of Gas Centrifuges in Stages	9
Reactor Installations for Nuclear Icebreakers: Origination Experience and Current Status	8
Population Irradiation Dose Assessment for 14C Emissions from NPP with RBMK-1000 and EGP-2 Reactors	8
Spent Nuclear Fuel Reprocessing and Nuclear Materials Recycling in Two-Component Nuclear Energy	7
Features of Radiation Swelling of Uranium-Plutonium Nitride Fuel in Experimental Fuel Rods with Helium and Lead Sublayer	7
Purification of Alkali-Metal Chlorides by Zone Recrystallization for Use in Pyrochemical Processing of Spent Nuclear Fuel	7
Efficiency Assessment of Nuclear Energy Development Scenarios for Russia Using Multi-Criteria Analysis	7
Environmental Radiation Safety Assessment in the Control Area at Nuclear Facilities	6
Integration of the Computational Validation Process for Reactor Equipment into a Single Information Space to Create Digital Doppelgangers of Nuclear Energy Facilities	6
Investigation of the Cooling of Water-Cooled and -Moderated Reactors Based on Electricity Generation Via Residual Heat in Emergency Situations with De-Energization	6
(α, n) Neutron Spectra on Thick Light Targets	5
Possibility of Burning Americium in Fast Reactors	5
Measurement of 186Re, 188Re, 189Re Yield on 186W Target Irradiation by 4He, 3He, 1H, and 2H	5
Recovery of Platinoids from NPP Spent Nuclear Fuel and Outlook for Their Use	5
Berkut Code Validation on Post-Reactor Studies of Irradiated Bn-600 Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel	5
OKBM Afrikantov Experience in Developing Methods and Computer Codes for Reliability Analysis and Probabilistic Safety Analysis of Nuclear Installations	5
Energy Outlook for Thermonuclear Fusion	5
Physical and Technical Problems of Reprocessed Uranium Enrichment with Repeated Recycling in Light-Water Reactors and Ways to Solve Them	5
Measurement of 186W(4He, p3n)186Re, 186W(4He, pn)188Re, 186W(4He, p)189Re Reaction Cross Sections By 4He Irradiation of 186W TARGET	4
Efficiency Studies of Heat-Transfer Intensifier Grids in TVSA-T Model Fuel Assemblies	4
VVER-1200 Tests in No. 6 Unit of the Novovoronezh NPP During Operation in a Daily Load Schedule	4

Competitiveness Assessment of Regenerated Uranium-Plutonium Remix Fuel in Thermal Reactors	4
Concept of a New High-Flux Periodic-Pulse Source of Neutrons Based on Neptunium	4
Optimal Multistream Cascades for Simultaneous Production of High-Enrichment Intermediate Components	4
Production of a Short-Lived Therapeutic α-Emitter 149Tb by Irradiation of Europium by 63 MeV α-Particles	4
Development of New Construction Materials for Innovative Reactor Installation Designs	4
Role of NPPs in the Russian Electricity Industry Taking into Account Carbon Emissions Limits	4
Reactor Installations with Sodium-Cooled Fast Reactors for Two-Component Nuclear Energy	4
Electrochemical Reduction of Uranium Dioxide in LiCl–Li2O Melt	4
Software Packages for Technical and Economic Modeling of Nuclear-Energy Systems: Status and Development Prospects	3
Nuclear Ship Reactor Installations: From Gen 1 to 5	3
Phase Diagram of the Quasibinary System LiF–NaF–KF–CeF3	3
Optimal Scale of Development of Nuclear Energy in the UES of Russia to 2050	3
Gas-Filled Ionization Chamber and Secondary-Emission Detector for Measuring γ-Ray Dose Rate	3
Dialysis Membranes Based on Microfiltration Elements for Separating the Components of Npp Radioactive Wastewater Via Precipitation	3
Electrochemical Decontamination of Irradiated Nuclear Graphite of Uranium-Graphite Nuclear Reactors	3
Methodological Issues and Results of Experimental and Computational Studies of Critical Heat Flows in RITM-200 Reactor Fuel Assemblies for Small NPP	3
Damaging Factors of a Nuclear Accident at the Nuclear Submarine K-431 in the Chazhma Bay	3
Neutronics Efficacy Evaluations of Lithium-Uranium and Lithium-Thorium Blankets in a Thermonuclear Plant	2
Strategy for the Development of Nuclear Energy in Russia and Environmental Matters	2
Occupational Irradiation Dose in 2017	2
Calculation and Experimental Determination of the Neutronics Characteristics of the IRT-T Research Reactor	2
Analysis of Gamma-Radiation Background Changes During Periods of Atmospheric Precipitation	2
Fission Gas Release from Irradiated Uranium-Plutonium Nitride Fuel	2
Investigation of the Corrosion Resistance of Nickel-Molybdenum Alloys in the Eutectic LiF–NaF–KF	2
Development of Fuel Pin with Uranium-Plutonium Nitride Fuel and Liquid-Metal Sublayer	2
Methods of Calculating the γ-Radiation Absorbed Dose Rate in Case of Radioactive Contamination of Meadow Biogeocenoses	2
Development of a Sorption Technology for Separating Uranium and Rare-Earth Elements	2
Nature of the Luminescence of SNC Steatite Ceramic	2
Patient Radiation Dose from Medical Diagnostic Imaging Procedures in 2018	2
High-Temperature Radiation Embrittlement of Neutron-Irradiated Austenitic Stainless Steels 08Kh18N10T, Ei-847, EP-172, and ChS-68	2
Cation Diffusion in a Crystallite of Mineral Illite	2
Fuel for VVER and PWR: Current Status and Prospects	2
Radiation Dose Assessment for Representative Biota Organisms in the Locale of NPP with VVER-1200	2
Reactor with Circulating Fuel Based on Molten Metal Fluorides for Np, Am, Cm Incineration	2
Thermohydraulics of Alkaline Liquid-Metal Coolant: A Retrospective-Perspective Look	2
Experience of Operating VVR-K with a Beryllium Reflector and Low-Enriched Uranium Fuel	2
Computational Validation of Experiments with Molten-Salt Thorium-Uranium Fuel Compositions in MBIR Test Loop	2
HTGR – New Prospects for Nuclear Energy	2
Method for Determining the Point Spread Function for a Digital Radiography System	2
Conditions for Reaching Radiation Equivalence of Native Raw Materials and Long-Lived Radioactive Waste in Nuclear Energy in Russia	2
Tritium Entry Into the Atmosphere with Emissions from NPP-VVER and Population Irradiation Dose Assessment	2
Modeling of the Mass Transfer of Steel Corrosion Products in Sodium Loops	2
Physical Modeling of Hydrodynamics and Heat Transfer in Liquid-Metal Cooled Fast Reactors	2
Modeling of Incompressible Fluid Flows in a Round Tube in Laminar, Transient, and Turbulent Regimes using the Conv-3d Code	2
Actual Developmental Problems of Small Energy Installations: SNPP Based on the SHELF-M Reactor Installation	2
Modeling of the ACE-L8 Experiment on Melt–Concrete Interaction	1
Certain Aspects of Using 15N-Enriched Mixed Uranium-Plutonium Nitride Fuel in a Fast-Reactor Fuel Cycle	1
Chemical Stability and Structural Characteristics of Cement Compounds with Radwaste Simulators after Ionizing Radiation Exposure	1
The Initial Stage of Closing the NFC of the Russian Two-Component Nuclear Power Engineering System	1
Computational Analysis and Evaluation of the Aftereffects of Fuel Assembly Drops Using Verified Deformation Models of Structural Materials	1

Radionuclides in the Soil of Typical Arctic Tundra and Beneath a Bird Colony Near the Russian Village of Barentsburg (Svalbard Archipelago)	1
Gas Centrifuge Cascade for Concentrating 235U in Additional Product and Purification of Processed Uranium Hexafluoride from 232,234,236U	1
Criteria for Optimizing Technical Solutions for NPP	1
Testing of Dispersion Type Fuel Rods with a Heat-Proof Meat with Controlled Porosity for Small Nuclear Power Plants	1
Prospective Accident-Tolerant Uranium-Molybdenum Metal Fuel	1
Determination of 137Cs Radioactive Contamination over Soil Depth Using a Xenon Spectrometer	1
Possibility of Irradiating in Russian Reactors the Plutonium Recycled From Mixed Uranium-Plutonium Fuel Fabricated in Marcoule (France)	1
Method of Integral Reliability Assessment of Equipment and Personnel of Long-Operating NPP Power Unit	1
Verification of the Aerosol/Lm Module in Experiments on Sodium Burning in Moist Air	1
Modeling of Gas-Phase Transport in Heavy Liquid-Metal Coolant Flow in the HYDRA-IBRAE/LM Thermohydraulic Code	1
Steel Cladding for VVER Fuel Pins in the Context of Accident-Tolerant Fuel: Prospects	1
Flow Simulation in Direct-Flow Gas Centrifuges	1
Reprocessed Uranium Hexafluoride Purification from 232,234,236U in Pentaflow Gas-Centrifuge Cascades	1
Study on the Performance of Primary Means of Measurement of the Hydrogen Concentration During Severe Accidents at NPP	1
MZK Program for Solving Stiff Systems in Nuclide Kinetics Problems	1
Security of Export Deliveries of Regenerated-Uranium Light-Water Reactor Fuel from the Standpoint of IAEA Safeguards	1
On the Matter of Different Approaches to a National Strategy for the Development of Nuclear Energy	1
Investigation of Local Damage Effect on Nb3Sn Superconductor Properties	1
NFC Russia Infrastructure Readiness Assessment for Development of PSKD-600 Power Reactors	1
Validation of a Module Based on the Les and DNS Approximations for Simulating Single-Phase Liquid-Metal Coolant Flow in Round Pipes	1
New Stage in Russia’s Nuclear Energy Strategy	1
Calculation of a Cascade System for the Purification of Regenerated Uranium Hexafluoride from 232,234,236U	1
Optimization of Two- and Three-Cascade Schemes for Efficient Separation of Stable Isotopes	1
Experimental Investigations of Coolant Mixing in TVSA with Intensifier-Grids	1
Effect of Irradiation on the Properties of Cement Compound as a Matrix for Solidifying High-Level Waste	1
Separative Cascade Shape Effect on the Isotopic Mixture Concentration in Cascade Holdup	1
Supercomputer Twin of a Nuclear Energy Installation: Developmental Approaches and Application Experience	1
Harmonization of Approaches to Evaluation of the Efficiency and Safe Operating Limits of Passive Catalytic Recombiners: System Model	1
42KhNM Alloy and Silicon Carbide as Material for Accident-Tolerant Fuel-Rod Cladding	1
Physical Chemistry and Technology of Alkaline Liquid-Metal Coolant: A Retrospective-Perspective Look	1
Economic Efficiency of Large, Medium, and Small Size NPP Including Construction Stage Risks	1
Investigation of Methods for Separating Thorium and Rare-Earth Elements in Nitric-Acid Leaching Solutions for Loparite Concentrate	1
Accident Tolerant Fuel with Chromium-Coated Fuel-Rod Cladding	1
Investigation of Fission Product Release from Irradiated Oxide and Nitride Nuclear Fuel on High-Temperature Heating in Helium Flow	1
Assessment of the Influence of BN-800 Operation on the Radioecological Situation in the Vicinity of Beloyarsk NPP	1
Mcu-PD Code Calculation of Personnel Irradiation Dose in an Accident with Coolant Leakage in Serviced Enclosures in NPP with VVER-1000	1
Influence of Acting Factors on the Thermal and Stress State of the Geological Structure of a Deep Burial Site for Radwaste	1
Radwaste Characteristics in Uranium-Plutonium Nuclear Fuel Production	1
Dual-Cascade Scheme with Additional Feed and Product Streams for Purification of Regenerated Uranium Hexafluoride from 232,234,236U	1
Environmental Risk Analysis of Radioactive Contamination of the Ol’khovskoe Marsh	1
Simulation of Two-Phase Flow of a Three-Component Mixture with Heat-and-Mass Transfer	1
Aerosol Formation During Laser Ablation in a Magnetic Field	1
Applicability Boron-Containing Materials Obtained by Self-Propagating High-Temperature Synthesis in Radiation Protection Technology	1
Methodology for Evaluating NPP Economic Indicators Including Safety	1
Study of the Technical Characteristics of Low-Enriched Uranium Hexafluoride in Long-Time Storage	1
Laser Device for Lowering the Uranium Detection Limit in Technological Environments of NPP	1
Detection of Indications of Nuclear Non-Proliferation Breaches By States Importing Fast Reactors with Closed NFC Installations	1
Comparison of D–D and D–T Tubes for Neutron Generators with Sorbed and Stuffed Targets	1
Neutron-Value Function Influence on the Accuracy of MCU-Aided Calculations of the Effective Delayed-Neutron Fraction and Prompt-Neutron Generation Time: An Investigation	1
Investigation of Discharge Generation Regimes in Penning Ion Sources Under Pulse-Packet Control	1
Homogenous Transmutation of 237Np, 241Am, 243Am in a Lead-Cooled Fast Reactor	1
Liquid Metal Research (History and Knowledge to be Preserved)	1
Short-Time Mechanical Properties of EP823-SH Ferrite-Martensite Steel After High-Dose Neutron Irradiation	1
Estimation of the Specific Activity of Iodine Release to Comply with the Base Principle of INPRO Methodology for PWR, BWR NPP	1
On an Optimal Minor-Actinide Transmutation Regime in a Molten-Salt Reactor	1
Prospects for using Chromium-Nickel Alloy 42KhNM in Different Types of Reactors	1
Analysis of the Long-Term Yearly Average Volumetric Activity of Radionuclides and the Yearly Absorbed Dose in the Surface Air with Continuous Radioactive Emissions (For Leningrad NPP-2)	1
Concentration of Tellurium Isotopes by a Multistage Scheme in an Ordinary Cascade of Gas Centrifuges	1
Thermohydraulic Calculation of VVER and SCWR Reactor Channels	1
Ignition of 4.8–12 Vol% Hydrogen Air Mixtures by Platinum-Coated Ceramic Particles	1
Experience in using Models of Pollutant Dispersal in an Urban Environment	1
Software Verification for Techno-Economic Simulation of Nuclear Energy Systems: Results and Recommendations	1
Radiation Safety Validation of a BREST-OD-300 Installation	1
Gas-Centrifuge Cascade Systems Optimization via Matrix Description of Step Connections in a General Scheme	1
Calculation of a System for Forming a Bremsstrahlung Beam in Discretely Falling Magnetic Field	1
Radioactive Contamination at the Epicenter of a Nuclear Accident and on the Territory of a Ship Repair Yard in Bukhta Chazhma	1
Celsist Subchannel Module Aided Simulation of Liquid-Metal Coolant Flow in Experimental FA	1
Radionuclide Composition of NPP Gas Emissions and Population Radiation Dose Assessment	1
Migration-Dosimetric Model of Grassy-Plant Irradiation Formation in Meadow Biogeocenoses under Constant Radioactive Fallout	1
Neutronics Calculations of Performance Enhancement of the Lithium-Uranium Blanket of a Tokamak Reactor	1
CONV-3D Code Aided Calculation of the Flow Parameters of Fuel-Rod Bundles	1
High-Temperature Behavior of Irradiated Dispersion Fuel Rods with 42KhNM-Alloy Cladding	1
Immobilization of Actinide Radwaste into a Perovskite-Like Matrix by Self-Propagating High-Temperature Synthesis	1
Nuclear Non-Proliferation Security on Exportation of Fast Reactors with a Closed Fuel Cycle	1
EVKLID/V1 Modeling of a Lead-Cooled Reactor Core with Water Vapor Ingress into the Coolant	0
Prospects of SNPPs in the electric power industry	0
Experimental Study of Departure from Nucleate Boiling on the Surface of a Molten Core Catcher Under Conditions of Boiling Borated Water with Debris	0
Refinement of the Parameters of a Reactor Installation and Thermohydraulic Characteristics of the Main Equipment, Based on Commissioning Results for a Power Unit with BN-800	0
Study of Effects Caused by the Neutron Value Function on Kinetic Functionals Using the MCU Software	0
Next-Generation Capacitor-Type Nuclear Batteries with Liquid Electrolyte	0

Hot Isostatic Pressing Temperature Effect on Chromium-Zirconium Copper Alloy Structure and Properties	0
Use of Burnable Absorbers in the PIK Reactor to Increase the Run Time	0
Adaptation of RT-1 Plant Technology to Processing of New Types of Spent Nuclear Fuel	0
Investigation of High-Temperature Uranium-Dioxide Kernel Creep in Nuclear Reactors	0
Dose Calculations for Herbaceous Plants: Comparison of Two Methods	0
Development of FA with High-Density Fuel for Foreign Research Nuclear Reactors of Russian Design	0
What Can and Cannot Be Expected from Tokamak Fusion	0
Allowing for a Shift of an Absorbing Element Relative to a Node of the Regular Lattice in Reactor Calculations by the Hetergeneous Method	0
OKBM Afrikantov Research and Testing Complex: From Creation to the Present Day	0
Mathematical Modeling in Designing a Chain-Type Cable-Laying Machine for NPP Equipment	0
Interrelation of the Iodine-Activity Limit in RBMK Coolant and the Number of Defective Fuel Pins	0
Promising Technologies for Liquid Radwaste Management in the Nuclear Industry	0
Representativeness Analysis of the Readings of the Coolant Temperature Control Channels at the Inlet and Outlet of the VVER-1200 Core of the First Power Unit of Novovoronezh NPP-2	0
Scientific and technical aspects of developing a RITM-200N innovative reactor for SNPPs	0
Investigation of Plasma-Chemical Synthesis of Complex Oxide Compositions for Dispersed Uranium-Plutonium Mixed Fuel	0
Appraisal Method for the Population Radiation Dose from 14C Emissions of Nuclear Enterprises	0
Stilbene-Based Spectrometer for Unfolding the Energy Distribution of Fast Neutron Sources	0
Isotopic Effect – Macroscopic Manifestation of the Strong Nuclear Long-Range Interaction	0
Cooldown Study of TVS-2M Model FA with Reflooding	0
Maintaining and Improving the Accuracy of Feed-Water Flow Measurement and Thermal Power Determination in NPP Reactor Units	0
230U Yield Measurement on 3,4He-Irradiated ThO2 Targets	0
Implementation of Parallel-Computing Algorithms for Systems with Distributed Memory in the EUKLID/V1 Integrated Computer Code	0
Development of a Large-Sized Highly Sensitive Detector Based on α-Si–p-i-n Heterostructures for Radonometers	0
Features of Impurity Distribution in the Crystallization of Ammonium Tetrafluoroberyllate	0
Calculation of the Flow Parameters in the Fuel Bundles of FA with Spacers by Means of the Conv-3D Code	0
Post-Reactor Studies of Fuel Rods with Uranium-Plutonium Nitride Fuel with Gas and Liquid-Metal Sublayer	0
Construction of a Theory of an Ideal Multicomponent Separating Cascade	0
Probabilistic Reliability Analysis of the Process Line Systems of the Fuel Fabrication/Refabrication Module of a Pilot-Demonstration Energy Complex	0
Modeling of an ACE-L4 experiment on the interaction of the melt with concrete used in the construction of VVER-1000 NPPs	0
Parametric Model of the Production Process of Radiopharmaceuticals	0
Methods for Estimating a Neutron Spectrum Using a Diamond Detector, Plastic Scintillator, and Set of Activation Detectors	0
Effect of the Electron-Emitter Parameters of a Pulsed Source of Light Penning Ions on the Extracted Current	0
Characteristics of ZnS(Ag) + 6LiF Scintillator-Based Detector Used as a Neutron Dosimeter	0
Pumping Equipment for Nuclear Energy and the Non-Nuclear Market	0
Neural Network Model of a Point Reactor with Feedback	0
Plasma Processing of Fuel Pellets	0
Mathematical Process-Control Model of Radioactive Waste Disposal by Self-Immersion in Geological Rocks	0
Heat-Exchange Regularities and Thermohydraulic Code Verification for Supercritical Pressure Water Cooled Reactors	0
General and Particular Separation Potentials for Multicomponent Mixtures	0
RBMK-1000 Lifespan Management and Development of Repair/Diagnostic Robotics	0
Tests of a Two-Stage Core at the KV-1 Test Facility: Physical Aspects and Results	0
Possibility of Capital Reserve Allocation for Nuclear-Risk Insurance Coverage on Transitioning to SMRs	0
Methodological Basis for the Modernization of Thermal Control of NPP–VVER	0
Arrangement of a Concrete Slab in the Backfill as a Means of Altering the Seismic Response of a Building Structure	0
Comparative Analysis of Transmutation in a Burner Reactor Based on the Salts LiF–NaF–KF and LiF–BeF2	0
Radiation and Radiological Consequences of a Hypothetical Nuclear Accident at a Nuclear Facility Located in the Positional-Home District of Atomflot	0
Thermal Insulation for AES-2006 Sealed Containment Protection from Passive Catalytic Hydrogen Recombiners	0
Solution of the Equations of Nuclide Kinetics	0
Purification of Regenerated Uranium Hexafluoride from 232, 234, 236U in a Double Cascade with an Additional Feeding	0
Modeling of Aerodynamics and Heat-and-Mass Transfer on Ventilation of Industrial Enclosures	0
Numerical Modeling of Delayed-Neutron Precursor Transport in a Sodium-Cooled Fast Reactor	0
Calculation and Justification of Biological Protection for Hot Cells with Reprocessed-99Mo Volume Enlargement at Karpov Research Institute of Physical Chemistry	0
MCU–RELAP Software Package for Analyzing Accidents and Non-Stationary Processes in the PIK Reactor	0
Development of CPS Mechanisms for Naval and Civilian Ship Nuclear Installations	0
Enhancement of Monitoring of Condensate-Feed Systems of NPP by Analytical Composition Control of Process Waters	0
Adaptation of CONV-3D Single-Phase Module for Modeling Turbulent Flow in Reactors in the Les Approximation	0
Space Nuclear Power Systems Startup Optimization Methods	0
ANIS-V3 Measuring-and-Computing Complex	0
Level-3 Probabilistic Safety Analysis for NPP Siting Decisions	0
Experimental Investigations of the Onset and Growth of a Heat-Transfer Crisis in a Full-Scale Cross-Sectional Model FA of the RITM-200 Reactor for Small NPP	0
Probabilistic Safety Analysis of Nuclear Installations of Different Types and Classes	0
Radiometric Assessment of Nuclear Fuel Burnup in the Romashka Reactor	0
Fast neutron spectrometer based on a diamond sensor detector	0
Methodological Problems in Assessing the Availability Indicators of NPP Power Units at the Design Stage	0
Development and Verification of 60Co Accrual Calculation and Management Methodology	0
Conversion of CPS Channels at the Leningrad NPP Power Units 3 and 4 for the Production of Radionuclides	0
Verification and Validation of a Thermohydraulics-Neutronics Software Package for Calculating Transient Regimes in Heavy-Water Reactor Installations	0
Position Sensitive Detectors with Particle-Type Identification for Recording Images of Neutron and Gamma Sources in Mixed Fields	0
Influence of Mass Transfer and Physicochemical Processes in the Working Fluid on Erosion–Corrosion of Equipment and Pipelines in Nuclear Power Plants	0
Efficiency Assessment of Investments in Nuclear Desalination of Seawater	0
Modeling of the Dynamics of Plasma Flows and Neutron Generation in a Portable Generator with a Laser-Plasma Ion Diode	0
Testing of Nonstationary VVER-1200 Operating Regimes in Belarusian NPP No. 1	0
Refueling System for Fast Reactors: Creation and Development	0
MCU-BR Software Verification by Critical BFS-2 Stand Experiments	0
CONV-3D Code-Aided Calculation of the Free-Convective Flow Parameters of Lead–Bismuth Alloy in a Cavity with a Transverse Temperature Gradient	0
Reactor Pressure Vessel Cooling Scheme: Selection and Validation for Small Nuclear Power Plants	0
Reactor Tests of High-Temperature Gas-Cooled Fuel Rods	0
Reactivity Measurement in the Prompt-Jump Approximation for the Neutron Flux	0
Sources and Types of the Debris Generated During Loss-of-Coolant Accidents at WWER NPPs	0
Procedure for Selecting a Variant of Dismantling and Handling of Activated Elements of a Reactor Plant During Decommissioning of NPP-VVER Units	0
Corrosion Resistance of Siliconized Graphite Based Structural Materials Under Decontamination Conditions	0
Assessment of the Level of Natural Circulation of VVER-1000 Coolant on the Basis of Experimental Data from the Balakovo NPP	0
Verification of a Mathematical Model of 12Kh18N9 Steel Deformation Under Dynamic Loading of Fuel Assemblies	0
Concept of Carbide Compaction of Mixed Uranium-Plutonium Fuel	0
Radon Flux Density Measurement on Rock Surfaces	0
Computer Simulation of Measurements of VVER-1200 Emergency Protection Efficacy	0
Laser Device for Monitoring NPP Level-IV Emergencies	0
Evaluation of the Earthworm Radiation Dose on Territory with Elevated Natural Radionuclide Content	0
Purification of Reprocessed Uranium from 232, 234U in an Additional Product with Feed Point Shifted Toward the Main Product	0
Development of a Focusing Device for Neutron Control in Nuclear Energetics	0
Predictive Assessment of the Effective Dose of Irradiation of the Rural Population with Constant Radioactive Emissions from Nuclear Power Plants	0
Computational Aspects of Core Neutronics Calculation of Sodium-Cooled Fast Reactor at the Core Destruction Stage	0
Aleksandrov Research Institute of Technology – Test Base for Developing, Testing, and Investigating Different Types of Nuclear Propulsion Plants Built for Different End Uses	0
Analysis of the Consequences of a Large Leak in a Steam Generator in a Two-Circuit Lead-Cooled Reactor Unit	0
Deformation of Experimental Fuel Pins with Improved Zirconium-Alloy Cladding in Reactor Tests	0