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 2022-05-01 to 2026-05-01.)

Article	Citations
Study of Effects Caused by the Neutron Value Function on Kinetic Functionals Using the MCU Software	12
Methodological Problems in Assessing the Availability Indicators of NPP Power Units at the Design Stage	7
Carbon oxides in fuel particles with uranium dioxide kernels	5
Modeling of an ACE-L4 experiment on the interaction of the melt with concrete used in the construction of VVER-1000 NPPs	5
Experimental studies of combustion processes of stratified and uniform hydrogen-air mixtures	4
Evaluation of the Earthworm Radiation Dose on Territory with Elevated Natural Radionuclide Content	4
Effects of changes in the coolant flow rate of the VVER reactor to the response from the self-powered neutron detectors of the in-core monitoring system: simulation of transient modes in the PRIM-AES	3
Neutronic investigation of ALFRED lead-Cooled fast reactor core using monte carlo modeling	3
Assembly of core for the IGRIK-2 solution pulse reactor	3
Leakage control of HTGR fuel using a weak irradiation technique	3
System for measuring the level and density of liquids in nuclear-safe devices for new spent nuclear fuel reprocessing facilities	3
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	3
Application of laser technologies for dismantling the pipelines of MIR loop channels	3
Aleksandrov Research Institute of Technology – Test Base for Developing, Testing, and Investigating Different Types of Nuclear Propulsion Plants Built for Different End Uses	3
Technology development and performance study of various thermoluminescent detectors	3
Response matrix simulation for a fast neutron spectrometer based on an organic scintillator	3
TERMIT technology for developing simulation systems of small nuclear power facilities	3
Promising Technologies for Liquid Radwaste Management in the Nuclear Industry	3
Improving the efficiency of a BREST-300 NPP using the thermal energy of natural gas	2
Testing of sodium-heated steam generator models at SSC RF-IPPE: from BN-350 to BN-1200	2
Computational analysis of a blackout accident at a decomissioned RBMK	2
Chemical control of coolants in heavy-water systems of a PIK reactor	2
Simulation of the removal of radioactive aerosols from the atmosphere of NPP containment by spray system droplets using the MAVR-TA code	2
Kinetic model of electrochemical aqueous coolant decontamination	2
Effects of Accident-Tolerant Nuclear Fuel on NPP Economic Parameters	2

Experimental Neutronics Investigations of Nuclear Propulsion Reactors on Prototype Test Bases	2
Validation of a Module Based on the Les and DNS Approximations for Simulating Single-Phase Liquid-Metal Coolant Flow in Round Pipes	2
System for measuring low flow rates of aggressive and radioactive liquids in radiochemical industry	2
Critical factors of an integrated approach to the economics of small modular reactors	2
ANN-based mathematical model for improving the accuracy of liquid flow measurements at nuclear power plants	2
Effects of the Thermal Exposure and Organosilicate Coating on the Properties of a Specialized Concrete for NPP Construction	2
Debatable issues on the derivation of the separation potential for multicomponent mixtures	2
Isolation of Intermediate-Mass Components of Spent Nuclear Fuel in a Direct-Flow Plasma Centrifuge	2
Development of a method for measuring the effective fraction of delayed neutrons using a 240Pu spontaneous fission source	2
A promising method for zinc injection into the coolant of water-cooled nuclear reactors	2
Tests of fuel elements with uranium-plutonium nitride fuel in an IGR pulsed reactor	2
Demand of fusion energy for tritium and the possibility of its production in nuclear reactors	2
Effects of Novovoronezh NPP-2 industrial development on the assessment of the external radiation dose to personnel	2
Development of a neural-network methodology for the safety justification of VVER reactors in manoeuvring modes	2
Adjustment of ROM code models for calculating the population exposure dose according to international recommendations	2
Prospects for application of robotics and digitalization in integral critical experiments at compact assembly machines	2
Experimental determination of the element release from aqueous media of spent nuclear fuel reprocessing into the gas phase under violated equipment integrity	2
Assessing the durability of nuclear plant elements under high‑frequency broadband loading	2
Modes of generating pulsed discharges in chambers with inertial electrostatic plasma confinement	2
Fire simulation in the main control room of Bushehr nuclear power plant using CFAST software	2
Study into the possibility of using two groups of accelerated preventive protection for VVER-1200 reactors	2
Engineering and physical design of a molten salt reactor for transmutation of Np, Am, and Cm from spent VVER fuel	1
Triple Cascade Arrangement for Purifying Regenerated Uranium Hexafluoride from 232,234,236U	1
Study of the Sensitivity of the Calculated Radiation Load on VVER-1000 Internals to the Uncertainty of Initial Data	1
Model for controlling the atmospheric parameters of the process box in the fabrication-refabrication module of the pilot demonstration energy complex	1
Auxiliary Demineralized and Potable Water Supplies from Seawater at El-Dabaa NPP (Egypt)	1
Neutronics Models for Integrated Testing of Transport NPP on Land-Based Prototype Testing Facilities	1
Characteristics of ZnS(Ag) + 6LiF Scintillator-Based Detector Used as a Neutron Dosimeter	1
Scientific and practical aspects of a radiation inspection for a decommissioned NPP unit	1
Measurement of the Yield of Protactinium Radioisotopes 230,232,233Pa on Irradiation of ThO2 Targets by 1,2H AND 3,4He Nuclei	1
Fast neutron spectrometer based on a diamond sensor detector	1
Corrosion of fuel rod claddings made of E110 alloy in reactors of nuclear icebreakers and small nuclear power plants	1
Thermophysical properties of VVER uranium-gadolinium fuel pellets with 6–10 wt% of gadolinium oxide	1
Research of the influence of the feed solution flow rate on the uranium refining in an extraction column cascade	1
Evolution of fast reactors. The role of a BN-350 reactor	1
KIR-TG code for interconnected thermo-hydraulic and neutron-physical test calculations of VVER-SKD reactors	1
Chemical Decontamination of the Primary Loops of Nuclear Propulsion Plants	1
Background for substantiating the 80-year service life of a commercial sodium-cooled fast reactor plant	1
Analysis of variation of neutronic and kinetic parameters of a Heavy Water Zero Power Reactor caused by changes in the fuel lattice pitch using MCNPX code	1
Investigation of the Properties of Uranium-Molybdenum Pellet Fuel for VVER	1
Sources and Types of the Debris Generated During Loss-of-Coolant Accidents at WWER NPPs	1
Mathematical model of a periodic pulsed reactor	1
Fast reactors with lead-bismuth and lead coolants	1
Optical Flowmeter for Measuring the Coolant Flow Rate in the Primary Loop of a Nuclear Reactor	1
A study of the coolant flow at the inlet to the fuel assembly of the RITM nuclear icebreaker reactor	1
Modeling of the Coolant Flow Distribution Over the Elements of a BREST-OD-300 Reactor Core	1
Ignition of 4.8–12 Vol% Hydrogen Air Mixtures by Platinum-Coated Ceramic Particles	1
Effective parameters of cascades with a given number of gas centrifuges in stages for stable isotope separation	1
Combined diagnostics of the technical state of mobile reflector in IBR-2 research reactor	1
Calculation of a square cascade using the bee colony algorithm	1

Forecast of tritium release into the environment during the normal operation of nuclear power plants	1
Concept of Carbide Compaction of Mixed Uranium-Plutonium Fuel	1
Extended one-group cross-section libraries in precision nuclide composition calculations of irradiated steel	1
Assessment of the Level of Natural Circulation of VVER-1000 Coolant on the Basis of Experimental Data from the Balakovo NPP	1
Mathematical Modeling in Designing a Chain-Type Cable-Laying Machine for NPP Equipment	1
Three-Liquid, Two-Phase, Per-Channel Thermohydraulics Code Subchannel-Na/V1.0 for Single-Phase Sodium-Coolant Flows and Heat-Transfer: Key Models	1
Prospects of artificial intelligence in nuclear industry	1
External and internal ignition of a hydrogen-air gas mixture induced by a recombiner	1
Sorption of Cs, Np, and Pu by the rocks of the Yeniseisky site depending on the temperature and ionic strength of Mg-K-phosphate leaching solutions	1
Numerical simulation of changes in the pH of the aqueous medium in the containment sump during design basis and beyond design basis accidents at NPPs with VVER-1200 reactors	1
A Comparative Study of the EP823 Steel Corrosion Resistance in Lead and Lead-Bismuth Coolants	1
Study of the coolant flow rate through the fuel assemblies of the IVV-2M reactor core. Part 1	1
Prospects for using lunar soil in the thermal scheme of a nuclear power plant with thermoelectric energy conversion	1
Prospects of SNPPs in the electric power industry	1
Monitoring of forces in reinforcement bundles of nuclear power plant containments and emergency load justification	1
Causes of Non-Stationary Vibrations of a Moving Reflector Shaft of the IBR-2 Research Reactor	1
Study of alkaline coolant boiling in the fuel assemblies of fast reactors in emergency modes with natural convection	1
Verification of the TARUSA-9 software for measuring the activity of fission products in the coolant of a pressurized water reactor	1
Non-destructive inspection for measuring helium concentration in fuel rods	1
3D Modeling of NPP Containment Medium Mixing During the Development of Severe Accidents	1
Fuel cycles with advanced dispersion fuel elements of high uranium density	1
Influence of the Edge Effect in Pipeline–Nozzle Welds During “Leak Before Break” Validation	1
Approaches to slowing down the kinetics of a fast reactor as a means of enhancing its self-protection properties	1
Comparative tests of chemical absorbents for neutralization of fluoride gases under low pressure conditions	1
Determination of conditions for reloading the solid blanket module of a hybrid fusion-fission reactor with uranium and thorium source materials	1
Nuclear power sources of floating power units for energy supply of the Far Eastern Federal District, Russian Federation	1
Online convergence forecast for axial xenon oscillations of the power density in VVER-1000 and -1200 reactors	1
Preparation for dismantling the liquid waste disposal system of MR and RFT research reactors	1
Concentration of Tellurium Isotopes by a Multistage Scheme in an Ordinary Cascade of Gas Centrifuges	1
Refining the Postulated Defectiveness of NPP Equipment and Pipelines Using Bayesian Procedures	1
230U Yield Measurement on 3,4He-Irradiated ThO2 Targets	1
Simulation of NPP cable gland leakage monitoring	1
Concentration of 95–97Mo and production of isotopically modified molybdenum in a multi-step scheme of a square cascade	1
Neural Network Model of a Point Reactor with Feedback	1
Development of a Risk Monitoring Model for NPPs with a VVER-440 Reactor	1
Laser Device for Monitoring NPP Level-IV Emergencies	1
Population Morbidity from Technogenic Environmental Contamination in Tashkent and Tashkent Region: Investigation Based on Data from Neutron Activation Analysis	1
Innovative technologies for immobilizing the sodium primary coolant of fast neutron reactors and processing liquid radioactive waste generated during reactor operation	1
Computer simulator for training students to control the dissolution process of the nuclear fuel cycle	1
Superconducting technologies for main power transmission lines and power output systems	1
Estimated efficiency of gas centrifuge cascade profiling for the feeding stream of stages	1
Velocity and temperature distribution along the normal to the heat-transfer surfaces of in-reactor units under natural convection (generalization of experimental data)	1
Magnetic insulation system for a laser-plasma ion diode of a portable neutron generator	1
Computer Simulation of Measurements of VVER-1200 Emergency Protection Efficacy	1
A solid blanket concept for a fusion-fission hybrid reactor plant producing nuclear fuel	1
Development of Combined Polymeric Materials for Detecting Neutrons of Various Energies	1
Use of burnable absorbers for reducing water exchange during the VVER liquid control	1
Immobilization of chloride radioactive waste using a phosphate glass composite material	1