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
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
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
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
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
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
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
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
230U Yield Measurement on 3,4He-Irradiated ThO2 Targets	1
Concentration of 95–97Mo and production of isotopically modified molybdenum in a multi-step scheme of a square cascade	1
Corrosion of fuel rod claddings made of E110 alloy in reactors of nuclear icebreakers and small nuclear power plants	1
Estimated efficiency of gas centrifuge cascade profiling for the feeding stream of stages	1
Superconducting technologies for main power transmission lines and power output systems	1
Comparative tests of chemical absorbents for neutralization of fluoride gases under low pressure conditions	1
Effects of the Thermal Exposure and Organosilicate Coating on the Properties of a Specialized Concrete for NPP Construction	1
Causes of Non-Stationary Vibrations of a Moving Reflector Shaft of the IBR-2 Research Reactor	1
Simulation of an absorption refrigerator operated in the passive heat removal system of a nuclear reactor	1
Effective parameters of cascades with a given number of gas centrifuges in stages for stable isotope separation	1
Prospects of artificial intelligence in nuclear industry	1
Optical Flowmeter for Measuring the Coolant Flow Rate in the Primary Loop of a Nuclear Reactor	1
Study of alkaline coolant boiling in the fuel assemblies of fast reactors in emergency modes with natural convection	1
Development of a hydrogen-air flame in a vertical channel with a horizontal diaphragm	1
Computer Simulation of Measurements of VVER-1200 Emergency Protection Efficacy	1
Cryogenic mesitylene-based moderator as an optimum solution for use in a DARIA compact neutron source	1
Ignition of 4.8–12 Vol% Hydrogen Air Mixtures by Platinum-Coated Ceramic Particles	1
Chemical Decontamination of the Primary Loops of Nuclear Propulsion Plants	1
Development of Combined Polymeric Materials for Detecting Neutrons of Various Energies	1
Study of the coolant flow rate through the fuel assemblies of the IVV-2M reactor core. Part 1	1
Concept of Carbide Compaction of Mixed Uranium-Plutonium Fuel	1
Determination of conditions for reloading the solid blanket module of a hybrid fusion-fission reactor with uranium and thorium source materials	1
Non-destructive inspection for measuring helium concentration in fuel rods	1
Simulation of NPP cable gland leakage monitoring	1
Characteristics of ZnS(Ag) + 6LiF Scintillator-Based Detector Used as a Neutron Dosimeter	1
Extended one-group cross-section libraries in precision nuclide composition calculations of irradiated steel	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
Three-Liquid, Two-Phase, Per-Channel Thermohydraulics Code Subchannel-Na/V1.0 for Single-Phase Sodium-Coolant Flows and Heat-Transfer: Key Models	1

Auxiliary Demineralized and Potable Water Supplies from Seawater at El-Dabaa NPP (Egypt)	1
Computer simulator for training students to control the dissolution process of the nuclear fuel cycle	1
A Comparative Study of the EP823 Steel Corrosion Resistance in Lead and Lead-Bismuth Coolants	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
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
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
A solid blanket concept for a fusion-fission hybrid reactor plant producing nuclear fuel	1
Sources and Types of the Debris Generated During Loss-of-Coolant Accidents at WWER NPPs	1
3D Modeling of NPP Containment Medium Mixing During the Development of Severe Accidents	1
Combined diagnostics of the technical state of mobile reflector in IBR-2 research reactor	1
Sub-channel analysis of fuel assemblies for innovative reactor design using the MATADOR software	1
Computational analysis of a blackout accident at a decomissioned RBMK	1
Laser Device for Monitoring NPP Level-IV Emergencies	1
Approaches to slowing down the kinetics of a fast reactor as a means of enhancing its self-protection properties	1
Magnetic insulation system for a laser-plasma ion diode of a portable neutron generator	1
Model for controlling the atmospheric parameters of the process box in the fabrication-refabrication module of the pilot demonstration energy complex	1
Nuclear power sources of floating power units for energy supply of the Far Eastern Federal District, Russian Federation	1
Scientific and practical aspects of a radiation inspection for a decommissioned NPP unit	1
Neural Network Model of a Point Reactor with Feedback	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
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
Assessment of the Level of Natural Circulation of VVER-1000 Coolant on the Basis of Experimental Data from the Balakovo NPP	1
Refining the Postulated Defectiveness of NPP Equipment and Pipelines Using Bayesian Procedures	1
Evolution of fast reactors. The role of a BN-350 reactor	1
Preparation for dismantling the liquid waste disposal system of MR and RFT research reactors	1
Engineering and physical design of a molten salt reactor for transmutation of Np, Am, and Cm from spent VVER fuel	1
Calculation of a square cascade using the bee colony algorithm	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
Study of the Sensitivity of the Calculated Radiation Load on VVER-1000 Internals to the Uncertainty of Initial Data	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
Prospects of SNPPs in the electric power industry	1
Modeling of the Coolant Flow Distribution Over the Elements of a BREST-OD-300 Reactor Core	1
Fast neutron spectrometer based on a diamond sensor detector	1
Innovative technologies for immobilizing the sodium primary coolant of fast neutron reactors and processing liquid radioactive waste generated during reactor operation	1
Background for substantiating the 80-year service life of a commercial sodium-cooled fast reactor plant	1
Influence of the Edge Effect in Pipeline–Nozzle Welds During “Leak Before Break” Validation	1
Thermophysical properties of VVER uranium-gadolinium fuel pellets with 6–10 wt% of gadolinium oxide	1
Development of large-scale purified inert atmosphere cells for the pyroprocessing treatment of spent nuclear fuel	1
Immobilization of chloride radioactive waste using a phosphate glass composite material	1
Use of burnable absorbers for reducing water exchange during the VVER liquid control	1
Triple Cascade Arrangement for Purifying Regenerated Uranium Hexafluoride from 232,234,236U	1
Mathematical model of a periodic pulsed reactor	1
A study of the coolant flow at the inlet to the fuel assembly of the RITM nuclear icebreaker reactor	1
Prospects for using lunar soil in the thermal scheme of a nuclear power plant with thermoelectric energy conversion	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
Fast reactors with lead-bismuth and lead coolants	1
Neutronics Models for Integrated Testing of Transport NPP on Land-Based Prototype Testing Facilities	1
Analytical simulation of sustainable development scenarios for global two-component nuclear power industry. Part 1. Thermal reactor scenarios	0
Investigation of the Operating Regimes of Penning Ion Sources in Inhomogeneous Magnetic Fields	0
Liquid Radwaste Denitration by Electrochemical Reduction of Nitric Acid	0
Reduction of the erbium content in RBMK-1000 fuel	0
Lessons learned from the experience of operating lead-bismuth nuclear power reactors	0
Role of the BOR-60 research reactor in the development of fast reactors	0
Results of BOR-60 reactor tests and post-reactor studies of experimental fuel rods with mixed uranium-plutonium nitride fuel	0
Experimental Investigations of Severe Accidents at Nuclear Power Plants	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
Techno-Economic Prognosis for the Manufacture of Fuel Assemblies with Mixed Uranium-Plutonium Fuel for the VVER-SKD Power Reactor	0
Decommissioning of fuel elements at the reactor of the “Akademik Lomonosov” floating thermal power plant	0
Evaluation of the effectiveness of investments in spent nuclear fuel reprocessing	0
Possible Distortions of Low-Temperature Monitoring of the Water Redox Potential in VVER Primary Loop	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
Radiation Survey of Reactor Hall Walls at NRC Kurchatov Institute	0
Thermophysical properties of uranium-erbium fuel for VVER reactors	0
Self-protection of fast lead-cooled reactors against the partial blockage of the core flow area	0
System of fuel cladding failure detection for the BREST-OD-300 reactor plant	0
A method for design a linear heat rate ramp limit curve for thermal reactor fuel rods	0
Fast reactors in the strategic nuclear power development scenarios of the Russian Federation	0
Calculation of a gas centrifuge cascade with loss of working substance in stages	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
ANIS-V3 Measuring-and-Computing Complex	0
Formation of intermetallics during the metallization of model nuclear fuel based on uranium dioxide containing oxides of rare earth metals and palladium	0
MCU–RELAP Software Package for Analyzing Accidents and Non-Stationary Processes in the PIK Reactor	0
Study of the coolant flow rate through the fuel assemblies of the IVV-2M reactor core. Part 2	0
Method of Calculating and Optimizing Multiflow Cascades for Separating Multicomponent Isotopic Mixtures	0
Development of Atomic-Hydrogen Energy Technologies in the Rosatom State Corporation	0
Key lessons from major radiation accidents for emergency response in agriculture	0
Determination of the dose rate from the pulse-height spectra of an airborne gamma-ray spectrometer based on an unmanned aerial vehicle	0

Tritium distribution between the primary circuit and associated systems of a VVER NPP power unit	0
Natural Suppression of Lif–Naf–Kf Corrosion Activity in a Liquid Salt Reactor	0
Modeling of the Dynamics of Plasma Flows and Neutron Generation in a Portable Generator with a Laser-Plasma Ion Diode	0
Change in the relative concentration of ion beam components passing through a high-current diode	0
Experimental and computational-theoretical capabilities of RFNC—VNIITF and the tasks of ensuring the safety of hydrogen energy technologies	0
Testing of a transportation and storage container model	0
Prospects for fusion neutron sources in the Russian nuclear power industry	0
Experimental study of the hydrogen leakage and ignition in a ventilated room	0
Validation of the steam generator model in the RASNAR-GAZ software for calculating the dynamics of a gas-cooled reactor plant	0
Neutron generators with an external target at the remote end of the neutron tube ion guide	0
Strength study of composite materials with boron-containing filler for neutron shielding	0
Methods for Estimating a Neutron Spectrum Using a Diamond Detector, Plastic Scintillator, and Set of Activation Detectors	0
Purification of alkaline liquid high-level radioactive waste from cesium using Fersal-MD sorbent	0
Optimal rotor radius of a separation gas centrifuge	0
Optimization of the square and squared-off cascades to separate stable isotopes using meta-heuristic algorithms	0
First Cryogenic Tests of Superfluid Helium Heat Exchanger for an Ultracold Neutron Source	0
Modeling of the ACE-L8 Experiment on Melt–Concrete Interaction	0
BM-U facility for simulating emergency processes involving the propagation and combustion of flammable gases	0
Effects of meteorological parameters on the intensity of tritium emission from spray cooling ponds	0
Optimization of spent nuclear fuel reprocessing for reducing radioactive waste	0
The role and position of HTGR reactor technology in the development of the Russian energy	0
Calculation of Multistage Schemes for Concentrating Isotopes in a Gas-Centrifuge Cascade with Variable Separation Factors	0
Flow formation features at the inlet to the fuel catridge of a ritm snpp reactor	0
Reduction of the Systematic Error of the Monte Carlo Method in MCU-Aided Calculations of Nuclear Reactors	0
Severe Accident Management at NPP-2006 Reactor Plants (Leningrad NPP-2)	0
Fiber-optic sensor for long-term remote monitoring of γ-radiation at nuclear power facilities	0
Testing of a VVER-1200 reactor in a daily load schedule mode at the 1st power unit of the Leningrad NPP-2	0
Certain Problems of Lengthened Cooldown of NPP–VVER Power Units in Accidents with Loss of Primary-Loop Coolant	0
Neural network assessment of thermal stresses in the pipelines of a VVER reactor plant	0
Validation of the EUCLID/V1 integrated computer code against the BOR-60 experimental data	0
Thermophysical properties of VVER uranium-gadolinium fuel pellets with 3.35, 5, and 8 wt % gadolinium oxide	0
Prospects of using neutron beams for gamma-resonance spectroscopy	0
Simulated contamination of concrete surfaces with radioactive substances generated during nuclear power plant operation	0
Uncertainty Assessment and Sensitivity Analysis in the Problems of Nuclide Kinetic Modeling Using the Sun Module of BPSD Software	0
Radiation and Radiological Consequences of a Hypothetical Nuclear Accident at a Nuclear Facility Located in the Positional-Home District of Atomflot	0
Results of experimental testing of a hydrometallurgical technology for reprocessing spent nuclear fuel of fast neutron reactors	0
New challenges for the steam-power cycle in power plants based on lead-cooled reactors	0
Estimation of the maximum mass of graphite removed during phased work on the management of RBMK-1000 resource characteristics	0
Stilbene-Based Spectrometer for Unfolding the Energy Distribution of Fast Neutron Sources	0
Computational-Theoretical Investigations of Thermophysical and Physicochemical Processes Occurring During Severe Accidents at NPP–VVER	0
Calculation of X-Ray Dose Loads in the Human Body Using Voxel Phantoms and the MCU Program	0
Methodological Basis for the Modernization of Thermal Control of NPP–VVER	0
New approaches to the separation and concentration of americium in high oxidation forms for the fractionation of high-level waste	0
Informativity of the Status Parameters for Fuel Rod Claddings of Transport NPPs	0
Establishment of protective action planning zones for nuclear power plants using the Level 3 Probabilistic Safety Assessment	0
Application of metal-ceramic uranium-molybdenum fuel in an aluminum matrix for research reactors	0
Simplified estimation of accumulated strain at ratcheting	0
Release of radioactive cesium to the environment during standard npp operations	0
The Initial Stage of Closing the NFC of the Russian Two-Component Nuclear Power Engineering System	0
Calculation and experimental analysis of BN-800 neutron-physical characteristics during the transition to mixed oxide fuel loading	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
Thermal-hydraulic model of the heavy liquid metal coolant—steam-water mixture flow	0
Analysis of criteria for transmutation as an effective method for removing hazardous radioactive waste	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
Method for utilizing contaminated fractions of reprocessed uranium enrichment in double cascade schemes	0
Development of approaches to regulatory safety in industrial water-electrolysis production of hydrogen at NPPs	0
Comparative analysis of thermal hydraulics in once-through steam-generating channels of helical and straight tubes	0
Engineering and physical design of a molten salt research reactor	0
E110-Type Zirconium Alloys – Dilatometric Determination of Solidus and Liquidus Temperatures	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
Immobilization of spent sorbent for separation of americium and curium into magnesium potassium phosphate compound	0
Development and testing of methods for extracting and conditioning accident elimination sorbents in the basements of the Fukushima Daiichi NPP	0
Analytical simulation of sustainable development scenarios for global two-component nuclear power industry. Part 2. Fast reactor scenarios	0
Neutronics Efficacy Evaluations of Lithium-Uranium and Lithium-Thorium Blankets in a Thermonuclear Plant	0
Fire protection system for sodium equipment rooms of BN reactors: operating experience and development trends	0
R&D Test Bench for Investigating the Dynamic Adsorption of Radon from Airflows	0
Maximally optimized countercurrent gas centrifuge with the offset feeding point	0
Determination of the Fast Neutron Fluence on a VVER-1200 Vessel Using a Computational Model Including the Monte Carlo Method	0
On the Matter of Different Approaches to a National Strategy for the Development of Nuclear Energy	0
Scientific and technical aspects of developing a RITM-200N innovative reactor for SNPPs	0
Membrane-Sorption Technology for Purification and Concentration of Low-Level Liquid Waste from Transport NPPs	0
Enthalpy and heat capacity of lead in a condensed state	0
Calculation model for separating a mixture of plutonium, americium, and curium in NaCl–2CsCl melt	0
Purification of Regenerated Uranium Hexafluoride from 232, 234, 236U in a Double Cascade with an Additional Feeding	0
Models of material deformation under dynamic impact as applied to various structural elements	0
A comparative analysis of the consequences of accidents at Chernobyl and Fukushima Daiichi (Japan) NPPs for agriculture and the environment	0
Coolant nuclid kinetics for fast reactors	0
Increased sensitivity of fuel cladding failure detection	0
Distribution of the effective dose of ionizing radiation in the central hall of the IGR reactor after startups	0
Aerodynamic model based on similarity numbers and computational fluid dynamics for coolant mixing in HTGR bottom plenum	0
Methodology for forming the VVER reactor parameter requirements in cycling power reactor tests	0
Effect of nuclear fuel composition on neutrons yield in high-energy-density plasma	0
Influence of Manufactured-Part Design and Gasket Material on the Tightness of Flanged Joints Under Sharp Thermal Cycles in the Environment	0
Corrosion tests of triuran disilicide fuel pellets	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
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
Nuclear power in accelerated economic growth scenarios	0
Low-Pressure Nanofiltration Systems for Decreasing Boric Acid Ingress Into Drain Water in NPP with VVER	0
Modeling and comparative assessment of scenarios for deployment of nuclear hydrogen production in russia. Part 1	0
Calculation analysis of a severe accident at a nuclear power plant with a sodium-cooled fast reactor	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
Gibbsite- and kuzelite-based matrix for the preservation of radioactive aqueous sodium nitrate concentrates	0
Development and demonstration of basics for plasma reprocessing of spent nuclear fuel	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
Development outlook for the reactor experimental base of the JSC “INM” after 2040	0