Atomic Energy

Article	Citations
Study of Effects Caused by the Neutron Value Function on Kinetic Functionals Using the MCU Software	21
Neutronic investigation of ALFRED lead-Cooled fast reactor core using monte carlo modeling	15
Technology development and performance study of various thermoluminescent detectors	11
Laser Device for Lowering the Uranium Detection Limit in Technological Environments of NPP	10
Methodological Problems in Assessing the Availability Indicators of NPP Power Units at the Design Stage	5
Evaluation of the Earthworm Radiation Dose on Territory with Elevated Natural Radionuclide Content	4
Experimental studies of combustion processes of stratified and uniform hydrogen-air mixtures	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
Radiometric Assessment of Nuclear Fuel Burnup in the Romashka Reactor	4
Response matrix simulation for a fast neutron spectrometer based on an organic scintillator	3
Electrochemical Reduction of Uranium Dioxide in LiCl–Li2O Melt	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
System for measuring the level and density of liquids in nuclear-safe devices for new spent nuclear fuel reprocessing facilities	3
Assembly of core for the IGRIK-2 solution pulse reactor	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
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
Applicability Boron-Containing Materials Obtained by Self-Propagating High-Temperature Synthesis in Radiation Protection Technology	3
Promising Technologies for Liquid Radwaste Management in the Nuclear Industry	2
Tests of fuel elements with uranium-plutonium nitride fuel in an IGR pulsed reactor	2
Critical factors of an integrated approach to the economics of small modular reactors	2
Experimental Neutronics Investigations of Nuclear Propulsion Reactors on Prototype Test Bases	2
System for measuring low flow rates of aggressive and radioactive liquids in radiochemical industry	2
TERMIT technology for developing simulation systems of small nuclear power facilities	2
Leakage control of HTGR fuel using a weak irradiation technique	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
Study into the possibility of using two groups of accelerated preventive protection for VVER-1200 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
Plasma Processing of Fuel Pellets	2
Effects of Novovoronezh NPP-2 industrial development on the assessment of the external radiation dose to personnel	2
Aerosol Formation During Laser Ablation in a Magnetic Field	2
Concentration of Intermediate Molybdenum Isotopes in a Cascade with a Specified Number of Gas Centrifuges in Steps	2
Application of laser technologies for dismantling the pipelines of MIR loop channels	2
Determination of conditions for reloading the solid blanket module of a hybrid fusion-fission reactor with uranium and thorium source materials	1
Preparation for dismantling the liquid waste disposal system of MR and RFT research reactors	1
Testing of sodium-heated steam generator models at SSC RF-IPPE: from BN-350 to BN-1200	1
Laser Device for Monitoring NPP Level-IV Emergencies	1
Refining the Postulated Defectiveness of NPP Equipment and Pipelines Using Bayesian Procedures	1
Triple Cascade Arrangement for Purifying Regenerated Uranium Hexafluoride from 232,234,236U	1
Study of the coolant flow rate through the fuel assemblies of the IVV-2M reactor core. Part 1	1
A promising method for zinc injection into the coolant of water-cooled nuclear reactors	1
Investigation of Plasma-Chemical Synthesis of Complex Oxide Compositions for Dispersed Uranium-Plutonium Mixed Fuel	1
Improving the efficiency of a BREST-300 NPP using the thermal energy of natural gas	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
Kinetic model of electrochemical aqueous coolant decontamination	1
Study of alkaline coolant boiling in the fuel assemblies of fast reactors in emergency modes with natural convection	1
Effects of the Thermal Exposure and Organosilicate Coating on the Properties of a Specialized Concrete for NPP Construction	1
Non-destructive inspection for measuring helium concentration in fuel rods	1
Technical and Economic Features of IAEA Safeguards Application at NPPs with a Fast Reactor and On-Site Fuel Cycle	1
Characteristics of ZnS(Ag) + 6LiF Scintillator-Based Detector Used as a Neutron Dosimeter	1
Optimization of Two- and Three-Cascade Schemes for Efficient Separation of Stable Isotopes	1
Research of the influence of the feed solution flow rate on the uranium refining in an extraction column cascade	1
Experimental determination of the element release from aqueous media of spent nuclear fuel reprocessing into the gas phase under violated equipment integrity	1
Computer simulator for training students to control the dissolution process of the nuclear fuel cycle	1
Computational analysis of a blackout accident at a decomissioned RBMK	1
Combined diagnostics of the technical state of mobile reflector in IBR-2 research reactor	1
Flow Simulation in Direct-Flow Gas Centrifuges	1
Model for controlling the atmospheric parameters of the process box in the fabrication-refabrication module of the pilot demonstration energy complex	1
Refinement of the Parameters of a Reactor Installation and Thermohydraulic Characteristics of the Main Equipment, Based on Commissioning Results for a Power Unit with BN-800	1
Neutronics Models for Integrated Testing of Transport NPP on Land-Based Prototype Testing Facilities	1
External and internal ignition of a hydrogen-air gas mixture induced by a recombiner	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
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
Corrosion Assessment of Core Catcher Vessel Housing Over NPP Operating Period	1
Nuclear power sources of floating power units for energy supply of the Far Eastern Federal District, Russian Federation	1
Prospects for application of robotics and digitalization in integral critical experiments at compact assembly machines	1
Concentration of 95–97Mo and production of isotopically modified molybdenum in a multi-step scheme of a square cascade	1
Assessing the durability of nuclear plant elements under high‑frequency broadband loading	1
Prospects of artificial intelligence in nuclear industry	1
Simulation of the removal of radioactive aerosols from the atmosphere of NPP containment by spray system droplets using the MAVR-TA code	1
A study of the coolant flow at the inlet to the fuel assembly of the RITM nuclear icebreaker reactor	1
Measurement of the Yield of Protactinium Radioisotopes 230,232,233Pa on Irradiation of ThO2 Targets by 1,2H AND 3,4He Nuclei	1
Assessment of the Level of Natural Circulation of VVER-1000 Coolant on the Basis of Experimental Data from the Balakovo NPP	1

Approaches to slowing down the kinetics of a fast reactor as a means of enhancing its self-protection properties	1
Fast reactors with lead-bismuth and lead coolants	1
Development of an Engineering Model of Fuel Pellet Sintering in Multi-Zone Furnaces	1
Experience of Operating an Integrated Selective-Sorption Liquid-Radwaste Reprocessing Plant at SRC Zvezdochka	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
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
Development of Combined Polymeric Materials for Detecting Neutrons of Various Energies	1
Concept of Carbide Compaction of Mixed Uranium-Plutonium Fuel	1
Online convergence forecast for axial xenon oscillations of the power density in VVER-1000 and -1200 reactors	1
Fuel cycles with advanced dispersion fuel elements of high uranium density	1
Debatable issues on the derivation of the separation potential for multicomponent mixtures	1
Extended one-group cross-section libraries in precision nuclide composition calculations of irradiated steel	1
Engineering and physical design of a molten salt reactor for transmutation of Np, Am, and Cm from spent VVER fuel	1
Modes of generating pulsed discharges in chambers with inertial electrostatic plasma confinement	1
Computational Analysis and Evaluation of the Aftereffects of Fuel Assembly Drops Using Verified Deformation Models of Structural Materials	1
Computer Simulation of Measurements of VVER-1200 Emergency Protection Efficacy	1
Effects of Accident-Tolerant Nuclear Fuel on NPP Economic Parameters	1
Construction of a Theory of an Ideal Multicomponent Separating Cascade	1
Development of a neural-network methodology for the safety justification of VVER reactors in manoeuvring modes	1
Thermophysical properties of VVER uranium-gadolinium fuel pellets with 6–10 wt% of gadolinium oxide	1
Isolation of Intermediate-Mass Components of Spent Nuclear Fuel in a Direct-Flow Plasma Centrifuge	1
Forecast of tritium release into the environment during the normal operation of nuclear power plants	1
Development of a method for measuring the effective fraction of delayed neutrons using a 240Pu spontaneous fission source	1
Neural Network Model of a Point Reactor with Feedback	1
Background for substantiating the 80-year service life of a commercial sodium-cooled fast reactor plant	1
230U Yield Measurement on 3,4He-Irradiated ThO2 Targets	1
Immobilization of chloride radioactive waste using a phosphate glass composite material	1
Prospects of SNPPs in the electric power industry	1
Fast neutron spectrometer based on a diamond sensor detector	1
Ignition of 4.8–12 Vol% Hydrogen Air Mixtures by Platinum-Coated Ceramic Particles	1
Sources and Types of the Debris Generated During Loss-of-Coolant Accidents at WWER NPPs	1
Detection of Indications of Nuclear Non-Proliferation Breaches By States Importing Fast Reactors with Closed NFC Installations	1
Features of coolant movement at the boundary of jacketless fuel assemblies with fuel rods of various diameters	0
Testing of a transportation and storage container model	0
Aerodynamic model based on similarity numbers and computational fluid dynamics for coolant mixing in HTGR bottom plenum	0
Key lessons from major radiation accidents for emergency response in agriculture	0
Comparative analysis of thermal hydraulics in once-through steam-generating channels of helical and straight tubes	0
Two-cascade scheme of gas centrifuges for the purification of reprocessed uranium hexafluoride from 232, 234, 236U	0
Study of the coolant flow rate through the fuel assemblies of the IVV-2M reactor core. Part 2	0
Analytical simulation of sustainable development scenarios for global two-component nuclear power industry. Part 1. Thermal reactor scenarios	0
Optimal rotor radius of a separation gas centrifuge	0
Influence of Vertical Rib Size on UF6 Desublimation in Vertical Submersible Tanks	0
New challenges for the steam-power cycle in power plants based on lead-cooled reactors	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
Transport-NPP Secondary-Loop Water-Chemistry Management Based on Ion-Exchange Sorbent Analysis	0
Low-Pressure Nanofiltration Systems for Decreasing Boric Acid Ingress Into Drain Water in NPP with VVER	0
System of fuel cladding failure detection for the BREST-OD-300 reactor plant	0
Optimization of spent nuclear fuel reprocessing for reducing radioactive waste	0
TERMIT – Technology of Automated Simulation – an Instrumental Graphic Environment for Developing Digital Twins, Training Simulators, and Simulating Complexes of Nuclear Propulsion Reactor Plants and N	0
Calculation model for separating a mixture of plutonium, americium, and curium in NaCl–2CsCl melt	0
Spectral Analysis in Neutron Distribution Problems in Weakly Coupled Systems	0
Fundamental approaches to reprocessing spent fuel particles of high temperature gas-cooled reactors	0
The Initial Stage of Closing the NFC of the Russian Two-Component Nuclear Power Engineering System	0
Adaptation of RT-1 Plant Technology to Processing of New Types of Spent Nuclear Fuel	0
Corrosion tests of triuran disilicide fuel pellets	0
A method for design a linear heat rate ramp limit curve for thermal reactor fuel rods	0
Development outlook for the reactor experimental base of the JSC “INM” after 2040	0
Calculation of Multistage Schemes for Concentrating Isotopes in a Gas-Centrifuge Cascade with Variable Separation Factors	0
Calculation and experimental analysis of BN-800 neutron-physical characteristics during the transition to mixed oxide fuel loading	0
Calculation of X-Ray Dose Loads in the Human Body Using Voxel Phantoms and the MCU Program	0
Method of Calculating and Optimizing Multiflow Cascades for Separating Multicomponent Isotopic Mixtures	0
Gibbsite- and kuzelite-based matrix for the preservation of radioactive aqueous sodium nitrate concentrates	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
Calculation of a gas centrifuge cascade with loss of working substance in stages	0
Influence of Manufactured-Part Design and Gasket Material on the Tightness of Flanged Joints Under Sharp Thermal Cycles in the Environment	0
Estimation of the Specific Activity of Iodine Release to Comply with the Base Principle of INPRO Methodology for PWR, BWR NPP	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
Parametric Model of the Production Process of Radiopharmaceuticals	0
Self-protection of fast lead-cooled reactors against the partial blockage of the core flow area	0
Analysis of criteria for transmutation as an effective method for removing hazardous radioactive waste	0
Nitriding and Carburization of a Mixed Nitride Uranium-Plutonium Fuel Pin Cladding	0
Reduction of the erbium content in RBMK-1000 fuel	0
Maximally optimized countercurrent gas centrifuge with the offset feeding point	0
Evaluation of the effectiveness of investments in spent nuclear fuel reprocessing	0
Release of radioactive cesium to the environment during standard npp operations	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
Technologies of Np, Am Afterburning in Fast Reactors with Mixed Uranium-Plutonium Nitride Fuel	0
Validation of the EUCLID/V1 integrated computer code against the BOR-60 experimental data	0
Decommissioning of fuel elements at the reactor of the “Akademik Lomonosov” floating thermal power plant	0
Use of Burnable Absorbers in the PIK Reactor to Increase the Run Time	0

Effects of meteorological parameters on the intensity of tritium emission from spray cooling ponds	0
The effect of charge accumulation in a dielectric under the action of bremsstrahlung with a photon energy above 1 MeV	0
Establishment of protective action planning zones for nuclear power plants using the Level 3 Probabilistic Safety Assessment	0
Neural network assessment of thermal stresses in the pipelines of a VVER reactor plant	0
Estimation of the maximum mass of graphite removed during phased work on the management of RBMK-1000 resource characteristics	0
Swelling of Intermetallic Uranium–Silumin Dispersion Fuel Composition in Experimental Fuel Rods of the SM Reactor	0
Assessment of external radiation doses to herbage under various distribution of radionuclides in the vertical soil profile	0
Development and testing of methods for extracting and conditioning accident elimination sorbents in the basements of the Fukushima Daiichi NPP	0
Formation of intermetallics during the metallization of model nuclear fuel based on uranium dioxide containing oxides of rare earth metals and palladium	0
Modeling of Aerodynamics and Heat-and-Mass Transfer on Ventilation of Industrial Enclosures	0
Cation Diffusion in a Crystallite of Mineral Illite	0
On the Matter of Different Approaches to a National Strategy for the Development of Nuclear Energy	0
Methods for Estimating a Neutron Spectrum Using a Diamond Detector, Plastic Scintillator, and Set of Activation Detectors	0
Calculation and experimental studies for substantiating the design of BREST-OD-300 reactor sampler	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
Development of Atomic-Hydrogen Energy Technologies in the Rosatom State Corporation	0
Calculation of a squared-off cascade for simultaneous concentration of intermediate components	0
Certain Aspects of Using 15N-Enriched Mixed Uranium-Plutonium Nitride Fuel in a Fast-Reactor Fuel Cycle	0
Scientific and technical aspects of developing a RITM-200N innovative reactor for SNPPs	0
Natural Suppression of Lif–Naf–Kf Corrosion Activity in a Liquid Salt Reactor	0
Environmental Risk Analysis of Radioactive Contamination of the Ol’khovskoe Marsh	0
Method for utilizing contaminated fractions of reprocessed uranium enrichment in double cascade schemes	0
Possible Distortions of Low-Temperature Monitoring of the Water Redox Potential in VVER Primary Loop	0
First Cryogenic Tests of Superfluid Helium Heat Exchanger for an Ultracold Neutron Source	0
Isotopic Mixture Properties and their Variation in the Separation Process	0
Thermal-hydraulic model of the heavy liquid metal coolant—steam-water mixture flow	0
Increased sensitivity of fuel cladding failure detection	0
Enthalpy and heat capacity of lead in a condensed state	0
Computational-Theoretical Investigations of Thermophysical and Physicochemical Processes Occurring During Severe Accidents at NPP–VVER	0
Liquid Radwaste Denitration by Electrochemical Reduction of Nitric Acid	0
Prospects of using neutron beams for gamma-resonance spectroscopy	0
Software Verification for Techno-Economic Simulation of Nuclear Energy Systems: Results and Recommendations	0
Role of the BOR-60 research reactor in the development of fast reactors	0
Tritium distribution between the primary circuit and associated systems of a VVER NPP power unit	0
Thermophysical properties of uranium-erbium fuel for VVER reactors	0
A comparative analysis of the consequences of accidents at Chernobyl and Fukushima Daiichi (Japan) NPPs for agriculture and the environment	0
Laser-induced breakdown spectrometry for product monitoring of spent nuclear fuel reprocessing	0
Determination of the Fast Neutron Fluence on a VVER-1200 Vessel Using a Computational Model Including the Monte Carlo Method	0
Nuclear power in accelerated economic growth scenarios	0
Application of metal-ceramic uranium-molybdenum fuel in an aluminum matrix for research reactors	0
Investigation of the Operating Regimes of Penning Ion Sources in Inhomogeneous Magnetic Fields	0
Determining the swelling of mixed nitride uranium-plutonium fuel based on the post-reactor studies of experimental BN-600 and BOR-60 fuel rods	0
The role and position of HTGR reactor technology in the development of the Russian energy	0
Reduction of the Systematic Error of the Monte Carlo Method in MCU-Aided Calculations of Nuclear Reactors	0
Methodological Basis for the Modernization of Thermal Control of NPP–VVER	0
Magnesium potassium phosphate matrix for solidification of a spent tributyl phosphate—dodecane simulant	0
Estimated Transmutation Efficiency in a Molten-Salt Burner Reactor	0
Purification of Regenerated Uranium Hexafluoride from 232, 234, 236U in a Double Cascade with an Additional Feeding	0
Heterogeneous burning of americium and neptunium in the core of a BN-1200 reactor	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
Optimal rotor length of a gas centrifuge	0
Lessons learned from the experience of operating lead-bismuth nuclear power reactors	0
BF3 for Compensation and Additional Emergency Protection in HTGR	0
Radiation and Radiological Consequences of a Hypothetical Nuclear Accident at a Nuclear Facility Located in the Positional-Home District of Atomflot	0
Engineering and physical design of a molten salt research reactor	0
Use of a refueling machine mast sipping system to detect leaking FAs during operational fuel cladding failure detection	0
Immobilization of spent sorbent for separation of americium and curium into magnesium potassium phosphate compound	0
Immobilization of Actinide Radwaste into a Perovskite-Like Matrix by Self-Propagating High-Temperature Synthesis	0
Justification of the CONV-3D code for simulating natural circulation of a lead-bismuth coolant in a hydraulic circuit	0
Distribution and Combustion of Hydrogen and Methane Mixtures with Air in a Container with Baffles: An Investigation	0
Testing of a VVER-1200 reactor in a daily load schedule mode at the 1st power unit of the Leningrad NPP-2	0
Prospects for fusion neutron sources in the Russian nuclear power industry	0
Correction to: Reduction of the Systematic Error of the Monte Carlo Method in MCU-Aided Calculations of Nuclear Reactors	0
Fiber-optic sensor for long-term remote monitoring of γ-radiation at nuclear power facilities	0
Techno-Economic Prognosis for the Manufacture of Fuel Assemblies with Mixed Uranium-Plutonium Fuel for the VVER-SKD Power Reactor	0
Harmonization of Approaches to Evaluation of the Efficiency and Safe Operating Limits of Passive Catalytic Recombiners: System Model	0
Approaches to the Assessment of the Cost for the Construction of Innovative Nuclear Power Facilities at the Early Stages of Design	0
Thermophysical properties of VVER uranium-gadolinium fuel pellets with 3.35, 5, and 8 wt % gadolinium oxide	0
Uncertainty Assessment and Sensitivity Analysis in the Problems of Nuclide Kinetic Modeling Using the Sun Module of BPSD Software	0
Purification of Alkali-Metal Chlorides by Zone Recrystallization for Use in Pyrochemical Processing of Spent Nuclear Fuel	0
Purification of alkaline liquid high-level radioactive waste from cesium using Fersal-MD sorbent	0
Fire protection system for sodium equipment rooms of BN reactors: operating experience and development trends	0
MCU–RELAP Software Package for Analyzing Accidents and Non-Stationary Processes in the PIK Reactor	0
Coolant nuclid kinetics for fast reactors	0
Experimental and computational-theoretical capabilities of RFNC—VNIITF and the tasks of ensuring the safety of hydrogen energy technologies	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
Evaluation of Onboard Radiometric System for Remote Sensing Detection of Heightened Radioactivity of Soil	0
Informativity of the Status Parameters for Fuel Rod Claddings of Transport NPPs	0
Radionuclides in the Soil of Typical Arctic Tundra and Beneath a Bird Colony Near the Russian Village of Barentsburg (Svalbard Archipelago)	0
Development and demonstration of basics for plasma reprocessing of spent nuclear fuel	0
Methodology for forming the VVER reactor parameter requirements in cycling power reactor tests	0
Voloxidated Spent Nuclear Fuel Metallization: Mathematical Model	0
Validation of the steam generator model in the RASNAR-GAZ software for calculating the dynamics of a gas-cooled reactor plant	0
Experimental Investigations of Severe Accidents at Nuclear Power Plants	0
Modeling of the ACE-L8 Experiment on Melt–Concrete Interaction	0
Evaluation of technological uncertainties using the sensitivity to nuclear data	0
Severe Accident Management at NPP-2006 Reactor Plants (Leningrad NPP-2)	0
Change of Interatomic Forces in Metal Under the Action Of Ionizing Radiation	0
Modeling of the Dynamics of Plasma Flows and Neutron Generation in a Portable Generator with a Laser-Plasma Ion Diode	0
Technical and economic aspects of a nuclear power engineering plant for hydrogen production	0
Neutronics Efficacy Evaluations of Lithium-Uranium and Lithium-Thorium Blankets in a Thermonuclear Plant	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
Radon Flux Density Measurement on Rock Surfaces	0
Development of approaches to regulatory safety in industrial water-electrolysis production of hydrogen at NPPs	0