OOIR: Observatory of International Research

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 2020-05-01 to 2024-05-01.)

Article	Citations
Brest Lead-Cooled Fast Reactor: From Concept to Technological Implementation	17
The World’s First Floating NPP: Origination and Direction of Future Development	12
Optimization of a Square Cascade of Centrifuges for Separation of Multicomponent Mixtures of Stable Isotopes	11
Purification of Alkali-Metal Chlorides by Zone Recrystallization for Use in Pyrochemical Processing of Spent Nuclear Fuel	9
Molybdenum Isotope Separation in a Cascade with a Specified Number of Gas Centrifuges in Stages	9
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	8
Reactor Installations for Nuclear Icebreakers: Origination Experience and Current Status	8
Features of Radiation Swelling of Uranium-Plutonium Nitride Fuel in Experimental Fuel Rods with Helium and Lead Sublayer	7
Efficiency Assessment of Nuclear Energy Development Scenarios for Russia Using Multi-Criteria Analysis	7
Investigation of the Cooling of Water-Cooled and -Moderated Reactors Based on Electricity Generation Via Residual Heat in Emergency Situations with De-Energization	6
Environmental Radiation Safety Assessment in the Control Area at Nuclear Facilities	6
(α, n) Neutron Spectra on Thick Light Targets	6
Development of New Construction Materials for Innovative Reactor Installation Designs	6
Energy Outlook for Thermonuclear Fusion	5
Measurement of 186Re, 188Re, 189Re Yield on 186W Target Irradiation by 4He, 3He, 1H, and 2H	5
Electrochemical Reduction of Uranium Dioxide in LiCl–Li2O Melt	5
Competitiveness Assessment of Regenerated Uranium-Plutonium Remix Fuel in Thermal Reactors	5
Efficiency Studies of Heat-Transfer Intensifier Grids in TVSA-T Model Fuel Assemblies	5
Physical and Technical Problems of Reprocessed Uranium Enrichment with Repeated Recycling in Light-Water Reactors and Ways to Solve Them	5
VVER-1200 Tests in No. 6 Unit of the Novovoronezh NPP During Operation in a Daily Load Schedule	5
Concept of a New High-Flux Periodic-Pulse Source of Neutrons Based on Neptunium	5
Possibility of Burning Americium in Fast Reactors	5
OKBM Afrikantov Experience in Developing Methods and Computer Codes for Reliability Analysis and Probabilistic Safety Analysis of Nuclear Installations	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

Production of a Short-Lived Therapeutic α-Emitter 149Tb by Irradiation of Europium by 63 MeV α-Particles	4
Phase Diagram of the Quasibinary System LiF–NaF–KF–CeF3	4
Role of NPPs in the Russian Electricity Industry Taking into Account Carbon Emissions Limits	4
Optimal Scale of Development of Nuclear Energy in the UES of Russia to 2050	4
Reactor Installations with Sodium-Cooled Fast Reactors for Two-Component Nuclear Energy	4
High-Temperature Radiation Embrittlement of Neutron-Irradiated Austenitic Stainless Steels 08Kh18N10T, Ei-847, EP-172, and ChS-68	3
Software Packages for Technical and Economic Modeling of Nuclear-Energy Systems: Status and Development Prospects	3
Methodological Issues and Results of Experimental and Computational Studies of Critical Heat Flows in RITM-200 Reactor Fuel Assemblies for Small NPP	3
Electrochemical Decontamination of Irradiated Nuclear Graphite of Uranium-Graphite Nuclear Reactors	3
Gas-Filled Ionization Chamber and Secondary-Emission Detector for Measuring γ-Ray Dose Rate	3
Damaging Factors of a Nuclear Accident at the Nuclear Submarine K-431 in the Chazhma Bay	3
Analysis of Gamma-Radiation Background Changes During Periods of Atmospheric Precipitation	3
Nuclear Ship Reactor Installations: From Gen 1 to 5	3
Criteria for Optimizing Technical Solutions for NPP	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
Conditions for Reaching Radiation Equivalence of Native Raw Materials and Long-Lived Radioactive Waste in Nuclear Energy in Russia	2
Fuel for VVER and PWR: Current Status and Prospects	2
MZK Program for Solving Stiff Systems in Nuclide Kinetics Problems	2
Reactor with Circulating Fuel Based on Molten Metal Fluorides for Np, Am, Cm Incineration	2
Laser Device for Lowering the Uranium Detection Limit in Technological Environments of NPP	2
Thermohydraulics of Alkaline Liquid-Metal Coolant: A Retrospective-Perspective Look	2
Harmonization of Approaches to Evaluation of the Efficiency and Safe Operating Limits of Passive Catalytic Recombiners: System Model	2
Experience of Operating VVR-K with a Beryllium Reflector and Low-Enriched Uranium Fuel	2
HTGR – New Prospects for Nuclear Energy	2
Ignition of 4.8–12 Vol% Hydrogen Air Mixtures by Platinum-Coated Ceramic Particles	2
Cation Diffusion in a Crystallite of Mineral Illite	2
Tritium Entry Into the Atmosphere with Emissions from NPP-VVER and Population Irradiation Dose Assessment	2
Investigation of the Corrosion Resistance of Nickel-Molybdenum Alloys in the Eutectic LiF–NaF–KF	2
Radiation Dose Assessment for Representative Biota Organisms in the Locale of NPP with VVER-1200	2
Actual Developmental Problems of Small Energy Installations: SNPP Based on the SHELF-M Reactor Installation	2
Neutronics Efficacy Evaluations of Lithium-Uranium and Lithium-Thorium Blankets in a Thermonuclear Plant	2
Computational Validation of Experiments with Molten-Salt Thorium-Uranium Fuel Compositions in MBIR Test Loop	2
Effect of Irradiation on the Properties of Cement Compound as a Matrix for Solidifying High-Level Waste	2
Calculation and Experimental Determination of the Neutronics Characteristics of the IRT-T Research Reactor	2
Fission Gas Release from Irradiated Uranium-Plutonium Nitride Fuel	2
On the Matter of Different Approaches to a National Strategy for the Development of Nuclear Energy	2
Physical Modeling of Hydrodynamics and Heat Transfer in Liquid-Metal Cooled Fast Reactors	2
Refueling System for Fast Reactors: Creation and Development	2
Methods of Calculating the γ-Radiation Absorbed Dose Rate in Case of Radioactive Contamination of Meadow Biogeocenoses	2
Prospective Accident-Tolerant Uranium-Molybdenum Metal Fuel	1
Investigation of Local Damage Effect on Nb3Sn Superconductor Properties	1
Computational Analysis and Evaluation of the Aftereffects of Fuel Assembly Drops Using Verified Deformation Models of Structural Materials	1
3D Modeling of NPP Containment Medium Mixing During the Development of Severe Accidents	1
Gas Centrifuge Cascade for Concentrating 235U in Additional Product and Purification of Processed Uranium Hexafluoride from 232,234,236U	1
Radiation Safety Validation of a BREST-OD-300 Installation	1
Testing of Dispersion Type Fuel Rods with a Heat-Proof Meat with Controlled Porosity for Small Nuclear Power Plants	1
Calculation of a System for Forming a Bremsstrahlung Beam in Discretely Falling Magnetic Field	1
Corrosion Resistance of Siliconized Graphite Based Structural Materials Under Decontamination Conditions	1

Radionuclide Composition of NPP Gas Emissions and Population Radiation Dose Assessment	1
Investigation of Fission Product Release from Irradiated Oxide and Nitride Nuclear Fuel on High-Temperature Heating in Helium Flow	1
Security of Export Deliveries of Regenerated-Uranium Light-Water Reactor Fuel from the Standpoint of IAEA Safeguards	1
Radioactive Contamination at the Epicenter of a Nuclear Accident and on the Territory of a Ship Repair Yard in Bukhta Chazhma	1
High-Temperature Behavior of Irradiated Dispersion Fuel Rods with 42KhNM-Alloy Cladding	1
Laser Device for Monitoring NPP Level-IV Emergencies	1
Investigation of Methods for Separating Thorium and Rare-Earth Elements in Nitric-Acid Leaching Solutions for Loparite Concentrate	1
NFC Russia Infrastructure Readiness Assessment for Development of PSKD-600 Power Reactors	1
Aerosol Formation During Laser Ablation in a Magnetic Field	1
Distribution and Combustion of Hydrogen and Methane Mixtures with Air in a Container with Baffles: An Investigation	1
TERMIT – Technology of Automated Simulation – an Instrumental Graphic Environment for Developing Digital Twins, Training Simulators, and Simulating Complexes of Nuclear Propulsion Reactor Plants and N	1
Modeling of Gas-Phase Transport in Heavy Liquid-Metal Coolant Flow in the HYDRA-IBRAE/LM Thermohydraulic Code	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
Liquid Metal Research (History and Knowledge to be Preserved)	1
Flow Simulation in Direct-Flow Gas Centrifuges	1
Utilization of spent nuclear fuel and transuranic actinides in a two-component nuclear power industry	1
Physical Chemistry and Technology of Alkaline Liquid-Metal Coolant: A Retrospective-Perspective Look	1
Applicability Boron-Containing Materials Obtained by Self-Propagating High-Temperature Synthesis in Radiation Protection Technology	1
Separative Cascade Shape Effect on the Isotopic Mixture Concentration in Cascade Holdup	1
Accident Tolerant Fuel with Chromium-Coated Fuel-Rod Cladding	1
Immobilization of Actinide Radwaste into a Perovskite-Like Matrix by Self-Propagating High-Temperature Synthesis	1
Supercomputer Twin of a Nuclear Energy Installation: Developmental Approaches and Application Experience	1
Method of Integral Reliability Assessment of Equipment and Personnel of Long-Operating NPP Power Unit	1
42KhNM Alloy and Silicon Carbide as Material for Accident-Tolerant Fuel-Rod Cladding	1
Steel Cladding for VVER Fuel Pins in the Context of Accident-Tolerant Fuel: Prospects	1
Development of Atomic-Hydrogen Energy Technologies in the Rosatom State Corporation	1
Reprocessed Uranium Hexafluoride Purification from 232,234,236U in Pentaflow Gas-Centrifuge Cascades	1
Economic Efficiency of Large, Medium, and Small Size NPP Including Construction Stage Risks	1
One-Group Cross-Sections of High-Threshold Reactions for Precision Neutronics Calculations	1
Experience in using Models of Pollutant Dispersal in an Urban Environment	1
Testing of Nonstationary VVER-1200 Operating Regimes in Belarusian NPP No. 1	1
Methodology for Evaluating NPP Economic Indicators Including Safety	1
Study on the Performance of Primary Means of Measurement of the Hydrogen Concentration During Severe Accidents at NPP	1
Validation of a Module Based on the Les and DNS Approximations for Simulating Single-Phase Liquid-Metal Coolant Flow in Round Pipes	1
Thermohydraulic Calculation of VVER and SCWR Reactor Channels	1
Detection of Indications of Nuclear Non-Proliferation Breaches By States Importing Fast Reactors with Closed NFC Installations	1
Virtual-Digital Model of NFC Closure for a Fast Reactor	1
Assessment of the Influence of BN-800 Operation on the Radioecological Situation in the Vicinity of Beloyarsk NPP	1
Activation of the Structural Materials of Fast-Neutron Generators	1
Optimization of Two- and Three-Cascade Schemes for Efficient Separation of Stable Isotopes	1
Influence of Acting Factors on the Thermal and Stress State of the Geological Structure of a Deep Burial Site for Radwaste	1
Certain Aspects of Using 15N-Enriched Mixed Uranium-Plutonium Nitride Fuel in a Fast-Reactor Fuel Cycle	1
Radionuclides in the Soil of Typical Arctic Tundra and Beneath a Bird Colony Near the Russian Village of Barentsburg (Svalbard Archipelago)	1
Environmental Risk Analysis of Radioactive Contamination of the Ol’khovskoe Marsh	1
Homogenous Transmutation of 237Np, 241Am, 243Am in a Lead-Cooled Fast Reactor	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
Neutronics Calculations of Performance Enhancement of the Lithium-Uranium Blanket of a Tokamak Reactor	1
Short-Time Mechanical Properties of EP823-SH Ferrite-Martensite Steel After High-Dose Neutron Irradiation	1
Experimental Investigations of Severe Accidents at Nuclear Power Plants	1
New Stage in Russia’s Nuclear Energy Strategy	1
Estimation of the Specific Activity of Iodine Release to Comply with the Base Principle of INPRO Methodology for PWR, BWR 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
Prospects for using Chromium-Nickel Alloy 42KhNM in Different Types of Reactors	1
Radwaste Characteristics in Uranium-Plutonium Nuclear Fuel Production	1
Concentration of Tellurium Isotopes by a Multistage Scheme in an Ordinary Cascade of Gas Centrifuges	1
Simulation of Two-Phase Flow of a Three-Component Mixture with Heat-and-Mass Transfer	1
Determination of 137Cs Radioactive Contamination over Soil Depth Using a Xenon Spectrometer	1
Development of Combined Polymeric Materials for Detecting Neutrons of Various Energies	1
Dual-Cascade Scheme with Additional Feed and Product Streams for Purification of Regenerated Uranium Hexafluoride from 232,234,236U	1
Study of the Technical Characteristics of Low-Enriched Uranium Hexafluoride in Long-Time Storage	1
Promising Technologies for Liquid Radwaste Management in the Nuclear Industry	1
Comparison of D–D and D–T Tubes for Neutron Generators with Sorbed and Stuffed Targets	1
CONV-3D Code Aided Calculation of the Flow Parameters of Fuel-Rod Bundles	1
Possibility of Irradiating in Russian Reactors the Plutonium Recycled From Mixed Uranium-Plutonium Fuel Fabricated in Marcoule (France)	1
Nuclear Non-Proliferation Security on Exportation of Fast Reactors with a Closed Fuel Cycle	1
Modeling of the ACE-L8 Experiment on Melt–Concrete Interaction	1
Software Verification for Techno-Economic Simulation of Nuclear Energy Systems: Results and Recommendations	1
Calculation of a Cascade System for the Purification of Regenerated Uranium Hexafluoride from 232,234,236U	1
Investigation of Discharge Generation Regimes in Penning Ion Sources Under Pulse-Packet Control	1
Maintaining and Improving the Accuracy of Feed-Water Flow Measurement and Thermal Power Determination in NPP Reactor Units	1
Experimental Investigations of Coolant Mixing in TVSA with Intensifier-Grids	1
On an Optimal Minor-Actinide Transmutation Regime in a Molten-Salt Reactor	1
Celsist Subchannel Module Aided Simulation of Liquid-Metal Coolant Flow in Experimental FA	1
The Initial Stage of Closing the NFC of the Russian Two-Component Nuclear Power Engineering System	1