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 2022-06-01 to 2026-06-01.)

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
Modeling of an ACE-L4 experiment on the interaction of the melt with concrete used in the construction of VVER-1000 NPPs	5
Carbon oxides in fuel particles with uranium dioxide kernels	5
System for measuring the level and density of liquids in nuclear-safe devices for new spent nuclear fuel reprocessing facilities	4
Experimental studies of combustion processes of stratified and uniform hydrogen-air mixtures	4
Technology development and performance study of various thermoluminescent detectors	3
Robotic technologies for decommissioning nuclear power plants and other nuclear facilities	3
Assembly of core for the IGRIK-2 solution pulse reactor	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
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
Response matrix simulation for a fast neutron spectrometer based on an organic scintillator	3
Application of laser technologies for dismantling the pipelines of MIR loop channels	3
TERMIT technology for developing simulation systems of small nuclear power facilities	3
Neutronic investigation of ALFRED lead-Cooled fast reactor core using monte carlo modeling	3
Evaluation of the Earthworm Radiation Dose on Territory with Elevated Natural Radionuclide Content	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
Leakage control of HTGR fuel using a weak irradiation technique	3
Testing of sodium-heated steam generator models at SSC RF-IPPE: from BN-350 to BN-1200	2
Prospects for application of robotics and digitalization in integral critical experiments at compact assembly machines	2
Development of a method for measuring the effective fraction of delayed neutrons using a 240Pu spontaneous fission source	2
Assessing the durability of nuclear plant elements under high‑frequency broadband loading	2
Simulation of the removal of radioactive aerosols from the atmosphere of NPP containment by spray system droplets using the MAVR-TA code	2
Study into the possibility of using two groups of accelerated preventive protection for VVER-1200 reactors	2
Tests of fuel elements with uranium-plutonium nitride fuel in an IGR pulsed reactor	2

Experimental Neutronics Investigations of Nuclear Propulsion Reactors on Prototype Test Bases	2
ANN-based mathematical model for improving the accuracy of liquid flow measurements at nuclear power plants	2
Improving the efficiency of a BREST-300 NPP using the thermal energy of natural gas	2
Experimental determination of the element release from aqueous media of spent nuclear fuel reprocessing into the gas phase under violated equipment integrity	2
Chemical control of coolants in heavy-water systems of a PIK reactor	2
Kinetic model of electrochemical aqueous coolant decontamination	2
Effects of Novovoronezh NPP-2 industrial development on the assessment of the external radiation dose to personnel	2
Demand of fusion energy for tritium and the possibility of its production in nuclear reactors	2
Validation of a Module Based on the Les and DNS Approximations for Simulating Single-Phase Liquid-Metal Coolant Flow in Round Pipes	2
Modes of generating pulsed discharges in chambers with inertial electrostatic plasma confinement	2
Effects of Accident-Tolerant Nuclear Fuel on NPP Economic Parameters	2
Adjustment of ROM code models for calculating the population exposure dose according to international recommendations	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 neural-network methodology for the safety justification of VVER reactors in manoeuvring modes	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
Fire simulation in the main control room of Bushehr nuclear power plant using CFAST software	2
A promising method for zinc injection into the coolant of water-cooled nuclear reactors	2
Effects of the Thermal Exposure and Organosilicate Coating on the Properties of a Specialized Concrete for NPP Construction	1
Magnetic insulation system for a laser-plasma ion diode of a portable neutron generator	1
Simulation of an absorption refrigerator operated in the passive heat removal system of a nuclear reactor	1
Nuclear power sources of floating power units for energy supply of the Far Eastern Federal District, Russian Federation	1
Prospects of artificial intelligence in nuclear industry	1
Scientific and practical aspects of a radiation inspection for a decommissioned NPP unit	1
Study of alkaline coolant boiling in the fuel assemblies of fast reactors in emergency modes with natural convection	1
Online convergence forecast for axial xenon oscillations of the power density in VVER-1000 and -1200 reactors	1
Monitoring of forces in reinforcement bundles of nuclear power plant containments and emergency load justification	1
Computer Simulation of Measurements of VVER-1200 Emergency Protection Efficacy	1
Engineering and physical design of a molten salt reactor for transmutation of Np, Am, and Cm from spent VVER fuel	1
Evolution of fast reactors. The role of a BN-350 reactor	1
Ignition of 4.8–12 Vol% Hydrogen Air Mixtures by Platinum-Coated Ceramic Particles	1
Study of the Sensitivity of the Calculated Radiation Load on VVER-1000 Internals to the Uncertainty of Initial Data	1
Calculation of a square cascade using the bee colony algorithm	1
Development of Combined Polymeric Materials for Detecting Neutrons of Various Energies	1
Modeling of the Coolant Flow Distribution Over the Elements of a BREST-OD-300 Reactor Core	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
Determination of conditions for reloading the solid blanket module of a hybrid fusion-fission reactor with uranium and thorium source materials	1
Innovative technologies for immobilizing the sodium primary coolant of fast neutron reactors and processing liquid radioactive waste generated during reactor operation	1
Extended one-group cross-section libraries in precision nuclide composition calculations of irradiated steel	1
Influence of the Edge Effect in Pipeline–Nozzle Welds During “Leak Before Break” Validation	1
Characteristics of ZnS(Ag) + 6LiF Scintillator-Based Detector Used as a Neutron Dosimeter	1
Development of large-scale purified inert atmosphere cells for the pyroprocessing treatment of spent nuclear fuel	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
Use of burnable absorbers for reducing water exchange during the VVER liquid control	1
Computer simulator for training students to control the dissolution process of the nuclear fuel cycle	1
Research of the influence of the feed solution flow rate on the uranium refining in an extraction column cascade	1
Mathematical model of a periodic pulsed reactor	1
Development of technological solutions for decommissioning equipment and systems of separate rooms in units no. 1 and 2 of the Leningrad NPP. Part 1	1
Prospects for using lunar soil in the thermal scheme of a nuclear power plant with thermoelectric energy conversion	1

Sources and Types of the Debris Generated During Loss-of-Coolant Accidents at WWER NPPs	1
Forecast of tritium release into the environment during the normal operation of nuclear power plants	1
KIR-TG code for interconnected thermo-hydraulic and neutron-physical test calculations of VVER-SKD reactors	1
Combined diagnostics of the technical state of mobile reflector in IBR-2 research reactor	1
Fuel cycles with advanced dispersion fuel elements of high uranium density	1
Development of a Risk Monitoring Model for NPPs with a VVER-440 Reactor	1
Computational analysis of a blackout accident at a decomissioned RBMK	1
Superconducting technologies for main power transmission lines and power output systems	1
Corrosion of fuel rod claddings made of E110 alloy in reactors of nuclear icebreakers and small nuclear power plants	1
Approaches to slowing down the kinetics of a fast reactor as a means of enhancing its self-protection properties	1
Causes of Non-Stationary Vibrations of a Moving Reflector Shaft of the IBR-2 Research Reactor	1
Comparative tests of chemical absorbents for neutralization of fluoride gases under low pressure conditions	1
Model for controlling the atmospheric parameters of the process box in the fabrication-refabrication module of the pilot demonstration energy complex	1
Effective parameters of cascades with a given number of gas centrifuges in stages for stable isotope separation	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
Optical Flowmeter for Measuring the Coolant Flow Rate in the Primary Loop of a Nuclear Reactor	1
Neural Network Model of a Point Reactor with Feedback	1
Refining the Postulated Defectiveness of NPP Equipment and Pipelines Using Bayesian Procedures	1
Development of a hydrogen-air flame in a vertical channel with a horizontal diaphragm	1
Assessment of the Level of Natural Circulation of VVER-1000 Coolant on the Basis of Experimental Data from the Balakovo NPP	1
Cryogenic mesitylene-based moderator as an optimum solution for use in a DARIA compact neutron source	1
Preparation for dismantling the liquid waste disposal system of MR and RFT research reactors	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
Chemical Decontamination of the Primary Loops of Nuclear Propulsion Plants	1
Prospects of SNPPs in the electric power industry	1
Study of the coolant flow rate through the fuel assemblies of the IVV-2M reactor core. Part 1	1
Fast neutron spectrometer based on a diamond sensor detector	1
Concept of Carbide Compaction of Mixed Uranium-Plutonium Fuel	1
Background for substantiating the 80-year service life of a commercial sodium-cooled fast reactor plant	1
Non-destructive inspection for measuring helium concentration in fuel rods	1
Simulation of NPP cable gland leakage monitoring	1
Thermophysical properties of VVER uranium-gadolinium fuel pellets with 6–10 wt% of gadolinium oxide	1
Mathematical Modeling in Designing a Chain-Type Cable-Laying Machine for NPP Equipment	1
External and internal ignition of a hydrogen-air gas mixture induced by a recombiner	1
Immobilization of chloride radioactive waste using a phosphate glass composite material	1
A Comparative Study of the EP823 Steel Corrosion Resistance in Lead and Lead-Bismuth Coolants	1
Auxiliary Demineralized and Potable Water Supplies from Seawater at El-Dabaa NPP (Egypt)	1
Triple Cascade Arrangement for Purifying Regenerated Uranium Hexafluoride from 232,234,236U	1
Verification of the TARUSA-9 software for measuring the activity of fission products in the coolant of a pressurized water reactor	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
A study of the coolant flow at the inlet to the fuel assembly of the RITM nuclear icebreaker reactor	1
A solid blanket concept for a fusion-fission hybrid reactor plant producing nuclear fuel	1
Neutronics Models for Integrated Testing of Transport NPP on Land-Based Prototype Testing Facilities	1
3D Modeling of NPP Containment Medium Mixing During the Development of Severe Accidents	1
Fast reactors with lead-bismuth and lead coolants	1
Concentration of 95–97Mo and production of isotopically modified molybdenum in a multi-step scheme of a square cascade	1
Sub-channel analysis of fuel assemblies for innovative reactor design using the MATADOR software	1
230U Yield Measurement on 3,4He-Irradiated ThO2 Targets	1
Laser Device for Monitoring NPP Level-IV Emergencies	1
Estimated efficiency of gas centrifuge cascade profiling for the feeding stream of stages	1