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

Article	Citations
Study of Effects Caused by the Neutron Value Function on Kinetic Functionals Using the MCU Software	22
Neutronic investigation of ALFRED lead-Cooled fast reactor core using monte carlo modeling	12
Technology development and performance study of various thermoluminescent detectors	11
Methodological Problems in Assessing the Availability Indicators of NPP Power Units at the Design Stage	6
Radiometric Assessment of Nuclear Fuel Burnup in the Romashka Reactor	5
Evaluation of the Earthworm Radiation Dose on Territory with Elevated Natural Radionuclide Content	4
Carbon oxides in fuel particles with uranium dioxide kernels	4
Modeling of an ACE-L4 experiment on the interaction of the melt with concrete used in the construction of VVER-1000 NPPs	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
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
Response matrix simulation for a fast neutron spectrometer based on an organic scintillator	3
Assembly of core for the IGRIK-2 solution pulse reactor	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
Experimental studies of combustion processes of stratified and uniform hydrogen-air mixtures	3
System for measuring the level and density of liquids in nuclear-safe devices for new spent nuclear fuel reprocessing facilities	3
Validation of a Module Based on the Les and DNS Approximations for Simulating Single-Phase Liquid-Metal Coolant Flow in Round Pipes	3
Development of a neural-network methodology for the safety justification of VVER reactors in manoeuvring modes	2
Leakage control of HTGR fuel using a weak irradiation technique	2
Study into the possibility of using two groups of accelerated preventive protection for VVER-1200 reactors	2
Plasma Processing of Fuel Pellets	2
Experimental Neutronics Investigations of Nuclear Propulsion Reactors on Prototype Test Bases	2
Effects of Accident-Tolerant Nuclear Fuel on NPP Economic Parameters	2
Tests of fuel elements with uranium-plutonium nitride fuel in an IGR pulsed reactor	2
TERMIT technology for developing simulation systems of small nuclear power facilities	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
Fire simulation in the main control room of Bushehr nuclear power plant using CFAST software	2
Modes of generating pulsed discharges in chambers with inertial electrostatic plasma confinement	2
Improving the efficiency of a BREST-300 NPP using the thermal energy of natural gas	2
Promising Technologies for Liquid Radwaste Management in the Nuclear Industry	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
Concentration of Intermediate Molybdenum Isotopes in a Cascade with a Specified Number of Gas Centrifuges in Steps	2
A promising method for zinc injection into the coolant of water-cooled nuclear reactors	2
Neural Network Model of a Point Reactor with Feedback	1
ANN-based mathematical model for improving the accuracy of liquid flow measurements at nuclear power plants	1
Chemical control of coolants in heavy-water systems of a PIK reactor	1
Effects of the Thermal Exposure and Organosilicate Coating on the Properties of a Specialized Concrete for NPP Construction	1
Construction of a Theory of an Ideal Multicomponent Separating Cascade	1
Experience of Operating an Integrated Selective-Sorption Liquid-Radwaste Reprocessing Plant at SRC Zvezdochka	1
Preparation for dismantling the liquid waste disposal system of MR and RFT research reactors	1
Computer Simulation of Measurements of VVER-1200 Emergency Protection Efficacy	1
Estimated efficiency of gas centrifuge cascade profiling for the feeding stream of stages	1
Study of the coolant flow rate through the fuel assemblies of the IVV-2M reactor core. Part 1	1
Development of Combined Polymeric Materials for Detecting Neutrons of Various Energies	1
Research of the influence of the feed solution flow rate on the uranium refining in an extraction column cascade	1
External and internal ignition of a hydrogen-air gas mixture induced by a recombiner	1
Online convergence forecast for axial xenon oscillations of the power density in VVER-1000 and -1200 reactors	1
Computer simulator for training students to control the dissolution process of the nuclear fuel cycle	1
Laser Device for Monitoring NPP Level-IV Emergencies	1
Measurement of the Yield of Protactinium Radioisotopes 230,232,233Pa on Irradiation of ThO2 Targets by 1,2H AND 3,4He Nuclei	1
Simulation of NPP cable gland leakage monitoring	1
Optimization of Two- and Three-Cascade Schemes for Efficient Separation of Stable Isotopes	1
Development of a Risk Monitoring Model for NPPs with a VVER-440 Reactor	1
Thermophysical properties of VVER uranium-gadolinium fuel pellets with 6–10 wt% of gadolinium oxide	1
KIR-TG code for interconnected thermo-hydraulic and neutron-physical test calculations of VVER-SKD reactors	1
Concentration of 95–97Mo and production of isotopically modified molybdenum in a multi-step scheme of a square cascade	1
Isolation of Intermediate-Mass Components of Spent Nuclear Fuel in a Direct-Flow Plasma Centrifuge	1
Sources and Types of the Debris Generated During Loss-of-Coolant Accidents at WWER NPPs	1
Adjustment of ROM code models for calculating the population exposure dose according to international recommendations	1
Approaches to slowing down the kinetics of a fast reactor as a means of enhancing its self-protection properties	1
Characteristics of ZnS(Ag) + 6LiF Scintillator-Based Detector Used as a Neutron Dosimeter	1
Assessing the durability of nuclear plant elements under high‑frequency broadband loading	1
Testing of sodium-heated steam generator models at SSC RF-IPPE: from BN-350 to BN-1200	1
Computational analysis of a blackout accident at a decomissioned RBMK	1
Fast neutron spectrometer based on a diamond sensor detector	1
Prospects for application of robotics and digitalization in integral critical experiments at compact assembly machines	1
Assessment of the Level of Natural Circulation of VVER-1000 Coolant on the Basis of Experimental Data from the Balakovo NPP	1
Non-destructive inspection for measuring helium concentration in fuel rods	1
Triple Cascade Arrangement for Purifying Regenerated Uranium Hexafluoride from 232,234,236U	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
Nuclear power sources of floating power units for energy supply of the Far Eastern Federal District, Russian Federation	1
Determination of conditions for reloading the solid blanket module of a hybrid fusion-fission reactor with uranium and thorium source materials	1
Flow Simulation in Direct-Flow Gas Centrifuges	1

Temperature Distribution and Heat Transfer in a Drained RBMK-1000 Fuel Channel During a Severe LOC Accident	1
Detection of Indications of Nuclear Non-Proliferation Breaches By States Importing Fast Reactors with Closed NFC Installations	1
Scientific and practical aspects of a radiation inspection for a decommissioned NPP unit	1
Refining the Postulated Defectiveness of NPP Equipment and Pipelines Using Bayesian Procedures	1
Corrosion of fuel rod claddings made of E110 alloy in reactors of nuclear icebreakers and small nuclear power plants	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
Monitoring of forces in reinforcement bundles of nuclear power plant containments and emergency load justification	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
Fuel cycles with advanced dispersion fuel elements of high uranium density	1
Kinetic model of electrochemical aqueous coolant decontamination	1
Simulation of the removal of radioactive aerosols from the atmosphere of NPP containment by spray system droplets using the MAVR-TA code	1
Development of an Engineering Model of Fuel Pellet Sintering in Multi-Zone Furnaces	1
Study of alkaline coolant boiling in the fuel assemblies of fast reactors in emergency modes with natural convection	1
Debatable issues on the derivation of the separation potential for multicomponent mixtures	1
Computational Analysis and Evaluation of the Aftereffects of Fuel Assembly Drops Using Verified Deformation Models of Structural Materials	1
Experimental determination of the element release from aqueous media of spent nuclear fuel reprocessing into the gas phase under violated equipment integrity	1
230U Yield Measurement on 3,4He-Irradiated ThO2 Targets	1
Immobilization of chloride radioactive waste using a phosphate glass composite material	1
Investigation of Plasma-Chemical Synthesis of Complex Oxide Compositions for Dispersed Uranium-Plutonium Mixed Fuel	1
Prospects of artificial intelligence in nuclear industry	1
Fast reactors with lead-bismuth and lead coolants	1
Engineering and physical design of a molten salt reactor for transmutation of Np, Am, and Cm from spent VVER fuel	1
Combined diagnostics of the technical state of mobile reflector in IBR-2 research reactor	1
Prospects of SNPPs in the electric power industry	1
Concept of Carbide Compaction of Mixed Uranium-Plutonium Fuel	1
Model for controlling the atmospheric parameters of the process box in the fabrication-refabrication module of the pilot demonstration energy complex	1
Background for substantiating the 80-year service life of a commercial sodium-cooled fast reactor plant	1
Concentration of Tellurium Isotopes by a Multistage Scheme in an Ordinary Cascade of Gas Centrifuges	1
Neutronics Models for Integrated Testing of Transport NPP on Land-Based Prototype Testing Facilities	1
Mathematical Modeling in Designing a Chain-Type Cable-Laying Machine for NPP Equipment	1
Calculated 137Cs Ingress into Groundwater via the Aeration Zone at the Demenka Test Site as a Result of the Accident at the Chernobyl Nuclear Power Plant	1
Evolution of fast reactors. The role of a BN-350 reactor	1
A study of the coolant flow at the inlet to the fuel assembly of the RITM nuclear icebreaker reactor	1
Forecast of tritium release into the environment during the normal operation of nuclear power plants	1
Extended one-group cross-section libraries in precision nuclide composition calculations of irradiated steel	1
A Comparative Study of the EP823 Steel Corrosion Resistance in Lead and Lead-Bismuth Coolants	1
Ignition of 4.8–12 Vol% Hydrogen Air Mixtures by Platinum-Coated Ceramic Particles	1
Development of a method for measuring the effective fraction of delayed neutrons using a 240Pu spontaneous fission source	1