Atomic Energy

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
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
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
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
Auxiliary Demineralized and Potable Water Supplies from Seawater at El-Dabaa NPP (Egypt)	1
Fuel cycles with advanced dispersion fuel elements of high uranium density	1
Scientific and practical aspects of a radiation inspection for a decommissioned NPP unit	1
Approaches to slowing down the kinetics of a fast reactor as a means of enhancing its self-protection properties	1
Thermophysical properties of VVER uranium-gadolinium fuel pellets with 6–10 wt% of gadolinium oxide	1
Corrosion of fuel rod claddings made of E110 alloy in reactors of nuclear icebreakers and small nuclear power plants	1
Determination of conditions for reloading the solid blanket module of a hybrid fusion-fission reactor with uranium and thorium source materials	1
Evolution of fast reactors. The role of a BN-350 reactor	1
Online convergence forecast for axial xenon oscillations of the power density in VVER-1000 and -1200 reactors	1
KIR-TG code for interconnected thermo-hydraulic and neutron-physical test calculations of VVER-SKD reactors	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
Preparation for dismantling the liquid waste disposal system of MR and RFT research reactors	1
Refining the Postulated Defectiveness of NPP Equipment and Pipelines Using Bayesian Procedures	1
Chemical Decontamination of the Primary Loops of Nuclear Propulsion Plants	1
230U Yield Measurement on 3,4He-Irradiated ThO2 Targets	1
Investigation of the Properties of Uranium-Molybdenum Pellet Fuel for VVER	1
Neural Network Model of a Point Reactor with Feedback	1
Mathematical model of a periodic pulsed reactor	1
Computer simulator for training students to control the dissolution process of the nuclear fuel cycle	1
Optical Flowmeter for Measuring the Coolant Flow Rate in the Primary Loop of a Nuclear Reactor	1
Estimated efficiency of gas centrifuge cascade profiling for the feeding stream of stages	1
Modeling of the Coolant Flow Distribution Over the Elements of a BREST-OD-300 Reactor Core	1
Computer Simulation of Measurements of VVER-1200 Emergency Protection Efficacy	1
Effective parameters of cascades with a given number of gas centrifuges in stages for stable isotope separation	1
Development of Combined Polymeric Materials for Detecting Neutrons of Various Energies	1
Calculation of a square cascade using the bee colony algorithm	1
Concept of Carbide Compaction of Mixed Uranium-Plutonium Fuel	1
Immobilization of chloride radioactive waste using a phosphate glass composite material	1
Mathematical Modeling in Designing a Chain-Type Cable-Laying Machine for NPP Equipment	1

Triple Cascade Arrangement for Purifying Regenerated Uranium Hexafluoride from 232,234,236U	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
External and internal ignition of a hydrogen-air gas mixture induced by a recombiner	1
Model for controlling the atmospheric parameters of the process box in the fabrication-refabrication module of the pilot demonstration energy complex	1
A Comparative Study of the EP823 Steel Corrosion Resistance in Lead and Lead-Bismuth Coolants	1
Neutronics Models for Integrated Testing of Transport NPP on Land-Based Prototype Testing Facilities	1
Study of the coolant flow rate through the fuel assemblies of the IVV-2M reactor core. Part 1	1
Monitoring of forces in reinforcement bundles of nuclear power plant containments and emergency load justification	1
Characteristics of ZnS(Ag) + 6LiF Scintillator-Based Detector Used as a Neutron Dosimeter	1
Measurement of the Yield of Protactinium Radioisotopes 230,232,233Pa on Irradiation of ThO2 Targets by 1,2H AND 3,4He Nuclei	1
Prospects for using lunar soil in the thermal scheme of a nuclear power plant with thermoelectric energy conversion	1
Fast neutron spectrometer based on a diamond sensor detector	1
Causes of Non-Stationary Vibrations of a Moving Reflector Shaft of the IBR-2 Research Reactor	1
Research of the influence of the feed solution flow rate on the uranium refining in an extraction column cascade	1
Verification of the TARUSA-9 software for measuring the activity of fission products in the coolant of a pressurized water reactor	1
Background for substantiating the 80-year service life of a commercial sodium-cooled fast reactor plant	1
3D Modeling of NPP Containment Medium Mixing During the Development of Severe Accidents	1
Sources and Types of the Debris Generated During Loss-of-Coolant Accidents at WWER NPPs	1
Influence of the Edge Effect in Pipeline–Nozzle Welds During “Leak Before Break” Validation	1
Fast reactors with lead-bismuth and lead coolants	1
Comparative tests of chemical absorbents for neutralization of fluoride gases under low pressure conditions	1
Nuclear power sources of floating power units for energy supply of the Far Eastern Federal District, Russian Federation	1
A study of the coolant flow at the inlet to the fuel assembly of the RITM nuclear icebreaker reactor	1
Concentration of Tellurium Isotopes by a Multistage Scheme in an Ordinary Cascade of Gas Centrifuges	1
Ignition of 4.8–12 Vol% Hydrogen Air Mixtures by Platinum-Coated Ceramic Particles	1
Concentration of 95–97Mo and production of isotopically modified molybdenum in a multi-step scheme of a square cascade	1
Simulation of NPP cable gland leakage monitoring	1
Combined diagnostics of the technical state of mobile reflector in IBR-2 research reactor	1
Development of a Risk Monitoring Model for NPPs with a VVER-440 Reactor	1
Forecast of tritium release into the environment during the normal operation of nuclear power plants	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
Extended one-group cross-section libraries in precision nuclide composition calculations of irradiated steel	1
Innovative technologies for immobilizing the sodium primary coolant of fast neutron reactors and processing liquid radioactive waste generated during reactor operation	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
Assessment of the Level of Natural Circulation of VVER-1000 Coolant on the Basis of Experimental Data from the Balakovo NPP	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
Superconducting technologies for main power transmission lines and power output systems	1
Prospects of artificial intelligence in nuclear industry	1
Magnetic insulation system for a laser-plasma ion diode of a portable neutron generator	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 solid blanket concept for a fusion-fission hybrid reactor plant producing nuclear fuel	1
Prospects of SNPPs in the electric power industry	1
Use of burnable absorbers for reducing water exchange during the VVER liquid control	1
Study of alkaline coolant boiling in the fuel assemblies of fast reactors in emergency modes with natural convection	1
Engineering and physical design of a molten salt reactor for transmutation of Np, Am, and Cm from spent VVER fuel	1
Non-destructive inspection for measuring helium concentration in fuel rods	1
Study of the Sensitivity of the Calculated Radiation Load on VVER-1000 Internals to the Uncertainty of Initial Data	1
Study of the coolant flow rate through the fuel assemblies of the IVV-2M reactor core. Part 2	0
Increasing the power of a VVER-1000 reactor due to economizing heating of feedwater in a water-to-water heat exchanger on a cold circulation loop	0
Predicting the composition and behavior of impurities in the primary coolant of the light-water small modular reactor based on the operating experience of propulsion reactors	0
Method of Calculating and Optimizing Multiflow Cascades for Separating Multicomponent Isotopic Mixtures	0
Effects of meteorological parameters on the intensity of tritium emission from spray cooling ponds	0
Flow formation features at the inlet to the fuel catridge of a ritm snpp reactor	0
MCU–RELAP Software Package for Analyzing Accidents and Non-Stationary Processes in the PIK Reactor	0
Neutronics Efficacy Evaluations of Lithium-Uranium and Lithium-Thorium Blankets in a Thermonuclear Plant	0
Informativity of the Status Parameters for Fuel Rod Claddings of Transport NPPs	0
Calculation of Multistage Schemes for Concentrating Isotopes in a Gas-Centrifuge Cascade with Variable Separation Factors	0
Certain Problems of Lengthened Cooldown of NPP–VVER Power Units in Accidents with Loss of Primary-Loop Coolant	0
Key lessons from major radiation accidents for emergency response in agriculture	0
Determination of the Fast Neutron Fluence on a VVER-1200 Vessel Using a Computational Model Including the Monte Carlo Method	0
Influence of Manufactured-Part Design and Gasket Material on the Tightness of Flanged Joints Under Sharp Thermal Cycles in the Environment	0
Scientific and technical aspects of developing a RITM-200N innovative reactor for SNPPs	0
Modeling of the Dynamics of Plasma Flows and Neutron Generation in a Portable Generator with a Laser-Plasma Ion Diode	0
Enthalpy and heat capacity of lead in a condensed state	0
New challenges for the steam-power cycle in power plants based on lead-cooled reactors	0
ANIS-V3 Measuring-and-Computing Complex	0
Environmental Risk Analysis of Radioactive Contamination of the Ol’khovskoe Marsh	0
Calculation of a gas centrifuge cascade with loss of working substance in stages	0
Distribution of the effective dose of ionizing radiation in the central hall of the IGR reactor after startups	0
Analysis of criteria for transmutation as an effective method for removing hazardous radioactive waste	0
First Cryogenic Tests of Superfluid Helium Heat Exchanger for an Ultracold Neutron Source	0
Effect of nuclear fuel composition on neutrons yield in high-energy-density plasma	0
Gibbsite- and kuzelite-based matrix for the preservation of radioactive aqueous sodium nitrate concentrates	0
DUM-R salinometer: innovative solution for in-circuit monitoring of water salt content in the secondary circuit of reactors for nuclear vessels, floating power units, and small modular reactor plants	0
Development of approaches to regulatory safety in industrial water-electrolysis production of hydrogen at NPPs	0
Certain Aspects of Using 15N-Enriched Mixed Uranium-Plutonium Nitride Fuel in a Fast-Reactor Fuel Cycle	0
Calculation analysis of a severe accident at a nuclear power plant with a sodium-cooled fast reactor	0
Modeling of the ACE-L8 Experiment on Melt–Concrete Interaction	0
Thermophysical properties of VVER uranium-gadolinium fuel pellets with 3.35, 5, and 8 wt % gadolinium oxide	0

CONV-3D Code-Aided Calculation of the Free-Convective Flow Parameters of Lead–Bismuth Alloy in a Cavity with a Transverse Temperature Gradient	0
Optimization of spent nuclear fuel reprocessing for reducing radioactive waste	0
Thermal-hydraulic model of the heavy liquid metal coolant—steam-water mixture flow	0
Testing of a VVER-1200 reactor in a daily load schedule mode at the 1st power unit of the Leningrad NPP-2	0
Swelling of Intermetallic Uranium–Silumin Dispersion Fuel Composition in Experimental Fuel Rods of the SM Reactor	0
Neural network assessment of thermal stresses in the pipelines of a VVER reactor plant	0
Method for utilizing contaminated fractions of reprocessed uranium enrichment in double cascade schemes	0
Purification of Regenerated Uranium Hexafluoride from 232, 234, 236U in a Double Cascade with an Additional Feeding	0
Development of Atomic-Hydrogen Energy Technologies in the Rosatom State Corporation	0
A comparative analysis of the consequences of accidents at Chernobyl and Fukushima Daiichi (Japan) NPPs for agriculture and the environment	0
Comparative analysis of thermal hydraulics in once-through steam-generating channels of helical and straight tubes	0
Lessons learned from the experience of operating lead-bismuth nuclear power reactors	0
Strength study of composite materials with boron-containing filler for neutron shielding	0
Role of the BOR-60 research reactor in the development of fast reactors	0
Computational-Theoretical Investigations of Thermophysical and Physicochemical Processes Occurring During Severe Accidents at NPP–VVER	0
Immobilization of spent sorbent for separation of americium and curium into magnesium potassium phosphate compound	0
R&D Test Bench for Investigating the Dynamic Adsorption of Radon from Airflows	0
Estimation of the maximum mass of graphite removed during phased work on the management of RBMK-1000 resource characteristics	0
Evaluation of the effectiveness of investments in spent nuclear fuel reprocessing	0
Tritium distribution between the primary circuit and associated systems of a VVER NPP power unit	0
Fire protection system for sodium equipment rooms of BN reactors: operating experience and development trends	0
Membrane-Sorption Technology for Purification and Concentration of Low-Level Liquid Waste from Transport NPPs	0
Methodological Basis for the Modernization of Thermal Control of NPP–VVER	0
Self-protection of fast lead-cooled reactors against the partial blockage of the core flow area	0
Nuclear power in accelerated economic growth scenarios	0
On the Matter of Different Approaches to a National Strategy for the Development of Nuclear Energy	0
Application of metal-ceramic uranium-molybdenum fuel in an aluminum matrix for research reactors	0
Uncertainty Assessment and Sensitivity Analysis in the Problems of Nuclide Kinetic Modeling Using the Sun Module of BPSD Software	0
Release of radioactive cesium to the environment during standard npp operations	0
Models of material deformation under dynamic impact as applied to various structural elements	0
Development and demonstration of basics for plasma reprocessing of spent nuclear fuel	0
Calculation of X-Ray Dose Loads in the Human Body Using Voxel Phantoms and the MCU Program	0
Use of a refueling machine mast sipping system to detect leaking FAs during operational fuel cladding failure detection	0
Prospects for fusion neutron sources in the Russian nuclear power industry	0
Natural Suppression of Lif–Naf–Kf Corrosion Activity in a Liquid Salt Reactor	0
Determination of the dose rate from the pulse-height spectra of an airborne gamma-ray spectrometer based on an unmanned aerial vehicle	0
Low-Pressure Nanofiltration Systems for Decreasing Boric Acid Ingress Into Drain Water in NPP with VVER	0
Change in the relative concentration of ion beam components passing through a high-current diode	0
Investigation of the Operating Regimes of Penning Ion Sources in Inhomogeneous Magnetic Fields	0
Establishment of protective action planning zones for nuclear power plants using the Level 3 Probabilistic Safety Assessment	0
Experimental study of the hydrogen leakage and ignition in a ventilated room	0
E110-Type Zirconium Alloys – Dilatometric Determination of Solidus and Liquidus Temperatures	0
Calculation model for separating a mixture of plutonium, americium, and curium in NaCl–2CsCl melt	0
Methods for Estimating a Neutron Spectrum Using a Diamond Detector, Plastic Scintillator, and Set of Activation Detectors	0
Reduction of the Systematic Error of the Monte Carlo Method in MCU-Aided Calculations of Nuclear Reactors	0
Development outlook for the reactor experimental base of the JSC “INM” after 2040	0
A method for design a linear heat rate ramp limit curve for thermal reactor fuel rods	0
Optimization of the square and squared-off cascades to separate stable isotopes using meta-heuristic algorithms	0
Aerodynamic model based on similarity numbers and computational fluid dynamics for coolant mixing in HTGR bottom plenum	0
Liquid Radwaste Denitration by Electrochemical Reduction of Nitric Acid	0
Development and testing of methods for extracting and conditioning accident elimination sorbents in the basements of the Fukushima Daiichi NPP	0
Radiation and Radiological Consequences of a Hypothetical Nuclear Accident at a Nuclear Facility Located in the Positional-Home District of Atomflot	0
BM-U facility for simulating emergency processes involving the propagation and combustion of flammable gases	0
Formation of intermetallics during the metallization of model nuclear fuel based on uranium dioxide containing oxides of rare earth metals and palladium	0
The role and position of HTGR reactor technology in the development of the Russian energy	0
Techno-Economic Prognosis for the Manufacture of Fuel Assemblies with Mixed Uranium-Plutonium Fuel for the VVER-SKD Power Reactor	0
Increased sensitivity of fuel cladding failure detection	0
Correction to: Reduction of the Systematic Error of the Monte Carlo Method in MCU-Aided Calculations of Nuclear Reactors	0
Thermophysical properties of uranium-erbium fuel for VVER reactors	0
Development of flow parts for MCP-1 and MCP-2 main circulating pumps of the BN-1200 reactor upon the experience of designing and operating main circulating pumps of BN-350, -600, -800 reactors	0
Radiation Survey of Reactor Hall Walls at NRC Kurchatov Institute	0
Methodology for forming the VVER reactor parameter requirements in cycling power reactor tests	0
Severe Accident Management at NPP-2006 Reactor Plants (Leningrad NPP-2)	0
Validation of the steam generator model in the RASNAR-GAZ software for calculating the dynamics of a gas-cooled reactor plant	0
Possible Distortions of Low-Temperature Monitoring of the Water Redox Potential in VVER Primary Loop	0
Fast reactors in the strategic nuclear power development scenarios of the Russian Federation	0
Allowing for a Shift of an Absorbing Element Relative to a Node of the Regular Lattice in Reactor Calculations by the Hetergeneous Method	0
Validation of the EUCLID/V1 integrated computer code against the BOR-60 experimental data	0
Experimental and computational-theoretical capabilities of RFNC—VNIITF and the tasks of ensuring the safety of hydrogen energy technologies	0
Fiber-optic sensor for long-term remote monitoring of γ-radiation at nuclear power facilities	0
Engineering and physical design of a molten salt research reactor	0
Coolant nuclid kinetics for fast reactors	0
Features of the coolant flow in a fuel rod bundle of the fuel assembly for the RITM-200S reactor of a modernized floating power unit	0
Results of experimental testing of a hydrometallurgical technology for reprocessing spent nuclear fuel of fast neutron reactors	0
Calculation and experimental analysis of BN-800 neutron-physical characteristics during the transition to mixed oxide fuel loading	0
Estimated Transmutation Efficiency in a Molten-Salt Burner Reactor	0
Stilbene-Based Spectrometer for Unfolding the Energy Distribution of Fast Neutron Sources	0
Analytical simulation of sustainable development scenarios for global two-component nuclear power industry. Part 1. Thermal reactor scenarios	0
The Initial Stage of Closing the NFC of the Russian Two-Component Nuclear Power Engineering System	0
New approaches to the separation and concentration of americium in high oxidation forms for the fractionation of high-level waste	0
Testing of a transportation and storage container model	0
Simplified estimation of accumulated strain at ratcheting	0
Reduction of the erbium content in RBMK-1000 fuel	0
System of fuel cladding failure detection for the BREST-OD-300 reactor plant	0
Time to radiological equivalence of radioactive waste and natural uranium feedstock at an increasing content of Np, Am, and Cm in long-lived radioactive waste	0
Results of BOR-60 reactor tests and post-reactor studies of experimental fuel rods with mixed uranium-plutonium nitride fuel	0
Neutron generators with an external target at the remote end of the neutron tube ion guide	0
Calculation of a cascade with the same number of gas centrifuges in stages and a given concentration of the target isotope in output streams	0
Experimental Study of Departure from Nucleate Boiling on the Surface of a Molten Core Catcher Under Conditions of Boiling Borated Water with Debris	0
Decommissioning of fuel elements at the reactor of the “Akademik Lomonosov” floating thermal power plant	0
Purification of alkaline liquid high-level radioactive waste from cesium using Fersal-MD sorbent	0
Prospects of using neutron beams for gamma-resonance spectroscopy	0
Optimal rotor radius of a separation gas centrifuge	0
Maximally optimized countercurrent gas centrifuge with the offset feeding point	0
Corrosion tests of triuran disilicide fuel pellets	0