Atomic Energy

Papers
(The TQCC of Atomic Energy is 1. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2020-11-01 to 2024-11-01.)
ArticleCitations
Brest Lead-Cooled Fast Reactor: From Concept to Technological Implementation19
The World’s First Floating NPP: Origination and Direction of Future Development15
Purification of Alkali-Metal Chlorides by Zone Recrystallization for Use in Pyrochemical Processing of Spent Nuclear Fuel13
Reactor Installations for Nuclear Icebreakers: Origination Experience and Current Status9
Spent Nuclear Fuel Reprocessing and Nuclear Materials Recycling in Two-Component Nuclear Energy9
Features of Radiation Swelling of Uranium-Plutonium Nitride Fuel in Experimental Fuel Rods with Helium and Lead Sublayer8
(α, n) Neutron Spectra on Thick Light Targets7
Development of New Construction Materials for Innovative Reactor Installation Designs7
Environmental Radiation Safety Assessment in the Control Area at Nuclear Facilities6
Electrochemical Reduction of Uranium Dioxide in LiCl–Li2O Melt6
Production of a Short-Lived Therapeutic α-Emitter 149Tb by Irradiation of Europium by 63 MeV α-Particles5
Role of NPPs in the Russian Electricity Industry Taking into Account Carbon Emissions Limits5
Competitiveness Assessment of Regenerated Uranium-Plutonium Remix Fuel in Thermal Reactors5
OKBM Afrikantov Experience in Developing Methods and Computer Codes for Reliability Analysis and Probabilistic Safety Analysis of Nuclear Installations5
Concept of a New High-Flux Periodic-Pulse Source of Neutrons Based on Neptunium5
Phase Diagram of the Quasibinary System LiF–NaF–KF–CeF34
Reactor with Circulating Fuel Based on Molten Metal Fluorides for Np, Am, Cm Incineration4
VVER-1200 Tests in No. 6 Unit of the Novovoronezh NPP During Operation in a Daily Load Schedule4
Measurement of 186W(4He, p3n)186Re, 186W(4He, pn)188Re, 186W(4He, p)189Re Reaction Cross Sections By 4He Irradiation of 186W TARGET4
Nuclear Ship Reactor Installations: From Gen 1 to 54
Criteria for Optimizing Technical Solutions for NPP4
Reactor Installations with Sodium-Cooled Fast Reactors for Two-Component Nuclear Energy4
Methodological Issues and Results of Experimental and Computational Studies of Critical Heat Flows in RITM-200 Reactor Fuel Assemblies for Small NPP4
Damaging Factors of a Nuclear Accident at the Nuclear Submarine K-431 in the Chazhma Bay3
Analysis of Gamma-Radiation Background Changes During Periods of Atmospheric Precipitation3
Post-Reactor Studies of Fuel Rods with Uranium-Plutonium Nitride Fuel with Gas and Liquid-Metal Sublayer3
Ignition of 4.8–12 Vol% Hydrogen Air Mixtures by Platinum-Coated Ceramic Particles3
Fission Gas Release from Irradiated Uranium-Plutonium Nitride Fuel3
Investigation of the Corrosion Resistance of Nickel-Molybdenum Alloys in the Eutectic LiF–NaF–KF3
Calculation of a Cascade System for the Purification of Regenerated Uranium Hexafluoride from 232,234,236U3
Promising Technologies for Liquid Radwaste Management in the Nuclear Industry3
Conditions for Reaching Radiation Equivalence of Native Raw Materials and Long-Lived Radioactive Waste in Nuclear Energy in Russia2
Cation Diffusion in a Crystallite of Mineral Illite2
On the Matter of Different Approaches to a National Strategy for the Development of Nuclear Energy2
Laser Device for Lowering the Uranium Detection Limit in Technological Environments of NPP2
Experience of Operating VVR-K with a Beryllium Reflector and Low-Enriched Uranium Fuel2
Nature of the Luminescence of SNC Steatite Ceramic2
Patient Radiation Dose from Medical Diagnostic Imaging Procedures in 20182
Short-Time Mechanical Properties of EP823-SH Ferrite-Martensite Steel After High-Dose Neutron Irradiation2
Fuel for VVER and PWR: Current Status and Prospects2
Modeling of Gas-Phase Transport in Heavy Liquid-Metal Coolant Flow in the HYDRA-IBRAE/LM Thermohydraulic Code2
Actual Developmental Problems of Small Energy Installations: SNPP Based on the SHELF-M Reactor Installation2
Harmonization of Approaches to Evaluation of the Efficiency and Safe Operating Limits of Passive Catalytic Recombiners: System Model2
Effect of Irradiation on the Properties of Cement Compound as a Matrix for Solidifying High-Level Waste2
Calculation and Experimental Determination of the Neutronics Characteristics of the IRT-T Research Reactor2
The Initial Stage of Closing the NFC of the Russian Two-Component Nuclear Power Engineering System2
Development of a Large-Sized Highly Sensitive Detector Based on α-Si–p-i-n Heterostructures for Radonometers2
MZK Program for Solving Stiff Systems in Nuclide Kinetics Problems2
Refueling System for Fast Reactors: Creation and Development2
Neutronics Efficacy Evaluations of Lithium-Uranium and Lithium-Thorium Blankets in a Thermonuclear Plant2
HTGR – New Prospects for Nuclear Energy2
Experimental Investigations of Severe Accidents at Nuclear Power Plants1
Corrosion Resistance of Siliconized Graphite Based Structural Materials Under Decontamination Conditions1
Distribution and Combustion of Hydrogen and Methane Mixtures with Air in a Container with Baffles: An Investigation1
Features of americium transmutation in a BN-1200M fast reactor1
Development and Verification of 60Co Accrual Calculation and Management Methodology1
Radionuclides in the Soil of Typical Arctic Tundra and Beneath a Bird Colony Near the Russian Village of Barentsburg (Svalbard Archipelago)1
Study of the Technical Characteristics of Low-Enriched Uranium Hexafluoride in Long-Time Storage1
Prospective Accident-Tolerant Uranium-Molybdenum Metal Fuel1
Thermohydraulic Calculation of VVER and SCWR Reactor Channels1
One-Group Cross-Sections of High-Threshold Reactions for Precision Neutronics Calculations1
Software Verification for Techno-Economic Simulation of Nuclear Energy Systems: Results and Recommendations1
Calculation of a System for Forming a Bremsstrahlung Beam in Discretely Falling Magnetic Field1
Maintaining and Improving the Accuracy of Feed-Water Flow Measurement and Thermal Power Determination in NPP Reactor Units1
Approaches to the Assessment of the Cost for the Construction of Innovative Nuclear Power Facilities at the Early Stages of Design1
Applicability Boron-Containing Materials Obtained by Self-Propagating High-Temperature Synthesis in Radiation Protection Technology1
Methodology for Evaluating NPP Economic Indicators Including Safety1
Level-3 Probabilistic Safety Analysis for NPP Siting Decisions1
Supercomputer Twin of a Nuclear Energy Installation: Developmental Approaches and Application Experience1
42KhNM Alloy and Silicon Carbide as Material for Accident-Tolerant Fuel-Rod Cladding1
Detection of Indications of Nuclear Non-Proliferation Breaches By States Importing Fast Reactors with Closed NFC Installations1
Development of Atomic-Hydrogen Energy Technologies in the Rosatom State Corporation1
Method of Calculating and Optimizing Multiflow Cascades for Separating Multicomponent Isotopic Mixtures1
Determination of 137Cs Radioactive Contamination over Soil Depth Using a Xenon Spectrometer1
Utilization of spent nuclear fuel and transuranic actinides in a two-component nuclear power industry1
Accident Tolerant Fuel with Chromium-Coated Fuel-Rod Cladding1
Economic Efficiency of Large, Medium, and Small Size NPP Including Construction Stage Risks1
Modeling of the ACE-L8 Experiment on Melt–Concrete Interaction1
Laser Device for Monitoring NPP Level-IV Emergencies1
Optimization of Two- and Three-Cascade Schemes for Efficient Separation of Stable Isotopes1
High-Temperature Behavior of Irradiated Dispersion Fuel Rods with 42KhNM-Alloy Cladding1
Liquid Metal Research (History and Knowledge to be Preserved)1
Aerosol Formation During Laser Ablation in a Magnetic Field1
Mcu-PD Code Calculation of Personnel Irradiation Dose in an Accident with Coolant Leakage in Serviced Enclosures in NPP with VVER-10001
Investigation of Methods for Separating Thorium and Rare-Earth Elements in Nitric-Acid Leaching Solutions for Loparite Concentrate1
Method of Integral Reliability Assessment of Equipment and Personnel of Long-Operating NPP Power Unit1
Flow Simulation in Direct-Flow Gas Centrifuges1
Radionuclide Composition of NPP Gas Emissions and Population Radiation Dose Assessment1
Neutronics Calculations of Performance Enhancement of the Lithium-Uranium Blanket of a Tokamak Reactor1
Computational Analysis and Evaluation of the Aftereffects of Fuel Assembly Drops Using Verified Deformation Models of Structural Materials1
Immobilization of Actinide Radwaste into a Perovskite-Like Matrix by Self-Propagating High-Temperature Synthesis1
Estimation of the Specific Activity of Iodine Release to Comply with the Base Principle of INPRO Methodology for PWR, BWR NPP1
Development of Combined Polymeric Materials for Detecting Neutrons of Various Energies1
Prospects for using Chromium-Nickel Alloy 42KhNM in Different Types of Reactors1
Nuclear Non-Proliferation Security on Exportation of Fast Reactors with a Closed Fuel Cycle1
Role of Nuclear Hydrogen Power Plants in Local Power Systems with Unconventional Energy Sources1
Certain Aspects of Using 15N-Enriched Mixed Uranium-Plutonium Nitride Fuel in a Fast-Reactor Fuel Cycle1
Investigation of Fission Product Release from Irradiated Oxide and Nitride Nuclear Fuel on High-Temperature Heating in Helium Flow1
Homogenous Transmutation of 237Np, 241Am, 243Am in a Lead-Cooled Fast Reactor1
Virtual-Digital Model of NFC Closure for a Fast Reactor1
Dual-Cascade Scheme with Additional Feed and Product Streams for Purification of Regenerated Uranium Hexafluoride from 232,234,236U1
Investigation of Discharge Generation Regimes in Penning Ion Sources Under Pulse-Packet Control1
Testing of Nonstationary VVER-1200 Operating Regimes in Belarusian NPP No. 11
TERMIT – Technology of Automated Simulation – an Instrumental Graphic Environment for Developing Digital Twins, Training Simulators, and Simulating Complexes of Nuclear Propulsion Reactor Plants and N1
Validation of a Module Based on the Les and DNS Approximations for Simulating Single-Phase Liquid-Metal Coolant Flow in Round Pipes1
3D Modeling of NPP Containment Medium Mixing During the Development of Severe Accidents1
Assessment of the Influence of BN-800 Operation on the Radioecological Situation in the Vicinity of Beloyarsk NPP1
Radiation Safety Validation of a BREST-OD-300 Installation1
Influence of Acting Factors on the Thermal and Stress State of the Geological Structure of a Deep Burial Site for Radwaste1
Simulation of Two-Phase Flow of a Three-Component Mixture with Heat-and-Mass Transfer1
Environmental Risk Analysis of Radioactive Contamination of the Ol’khovskoe Marsh1
Restoration of the Isotopic Composition of Regenerated Uranium in Ordinary and Pentastream Gas-Centrifuge Cascades1
Construction of a Theory of an Ideal Multicomponent Separating Cascade1
Neutron-Value Function Influence on the Accuracy of MCU-Aided Calculations of the Effective Delayed-Neutron Fraction and Prompt-Neutron Generation Time: An Investigation1
New Stage in Russia’s Nuclear Energy Strategy1
Gas Centrifuge Cascade for Concentrating 235U in Additional Product and Purification of Processed Uranium Hexafluoride from 232,234,236U1
NFC Russia Infrastructure Readiness Assessment for Development of PSKD-600 Power Reactors1
Testing of Dispersion Type Fuel Rods with a Heat-Proof Meat with Controlled Porosity for Small Nuclear Power Plants1
Fast Reactor Aided Adjustment of Plutonium Isotope Composition1
Concentration of Tellurium Isotopes by a Multistage Scheme in an Ordinary Cascade of Gas Centrifuges1
Experimental Investigations of Coolant Mixing in TVSA with Intensifier-Grids1
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