Atomic Energy

Article	Citations
Carbon oxides in fuel particles with uranium dioxide kernels	19
Radiometric Assessment of Nuclear Fuel Burnup in the Romashka Reactor	14
Methodological Problems in Assessing the Availability Indicators of NPP Power Units at the Design Stage	11
Study of Effects Caused by the Neutron Value Function on Kinetic Functionals Using the MCU Software	7
Evaluation of the Earthworm Radiation Dose on Territory with Elevated Natural Radionuclide Content	5
Experimental studies of combustion processes of stratified and uniform hydrogen-air mixtures	4
Neutronic investigation of ALFRED lead-Cooled fast reactor core using monte carlo modeling	4
Response matrix simulation for a fast neutron spectrometer based on an organic scintillator	4
Laser Device for Lowering the Uranium Detection Limit in Technological Environments of NPP	4
Modeling of an ACE-L4 experiment on the interaction of the melt with concrete used in the construction of VVER-1000 NPPs	4
Technology development and performance study of various thermoluminescent detectors	4
Calculation of the Flow Parameters in the Fuel Bundles of FA with Spacers by Means of the Conv-3D Code	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
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
Fire simulation in the main control room of Bushehr nuclear power plant using CFAST software	3
Validation of a Module Based on the Les and DNS Approximations for Simulating Single-Phase Liquid-Metal Coolant Flow in Round Pipes	3
Electrochemical Reduction of Uranium Dioxide in LiCl–Li2O Melt	3
Applicability Boron-Containing Materials Obtained by Self-Propagating High-Temperature Synthesis in Radiation Protection Technology	3
Assembly of core for the IGRIK-2 solution pulse reactor	2
Plasma Processing of Fuel Pellets	2
Critical factors of an integrated approach to the economics of small modular reactors	2
Application of laser technologies for dismantling the pipelines of MIR loop channels	2
Promising Technologies for Liquid Radwaste Management in the Nuclear Industry	2
Aerosol Formation During Laser Ablation in a Magnetic Field	2

Demand of fusion energy for tritium and the possibility of its production in nuclear reactors	2
Leakage control of HTGR fuel using a weak irradiation technique	2
Tests of fuel elements with uranium-plutonium nitride fuel in an IGR pulsed reactor	2
Study into the possibility of using two groups of accelerated preventive protection for VVER-1200 reactors	2
TERMIT technology for developing simulation systems of small nuclear power facilities	2
System for measuring low flow rates of aggressive and radioactive liquids in radiochemical industry	2
Development of a neural-network methodology for the safety justification of VVER reactors in manoeuvring modes	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
Refining the Postulated Defectiveness of NPP Equipment and Pipelines Using Bayesian Procedures	1
Improving the efficiency of a BREST-300 NPP using the thermal energy of natural gas	1
Concentration of 95–97Mo and production of isotopically modified molybdenum in a multi-step scheme of a square cascade	1
Model-Measuring Approach to Improving Aerosol Radiation Safety Validation Mechanisms	1
Optimization of Two- and Three-Cascade Schemes for Efficient Separation of Stable Isotopes	1
Representativeness Analysis of the Readings of the Coolant Temperature Control Channels at the Inlet and Outlet of the VVER-1200 Core of the First Power Unit of Novovoronezh NPP-2	1
Simulation of the removal of radioactive aerosols from the atmosphere of NPP containment by spray system droplets using the MAVR-TA code	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
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
Combined diagnostics of the technical state of mobile reflector in IBR-2 research reactor	1
Concept of Carbide Compaction of Mixed Uranium-Plutonium Fuel	1
Chemical control of coolants in heavy-water systems of a PIK reactor	1
Flow Simulation in Direct-Flow Gas Centrifuges	1
Detection of Indications of Nuclear Non-Proliferation Breaches By States Importing Fast Reactors with Closed NFC Installations	1
Investigation of Plasma-Chemical Synthesis of Complex Oxide Compositions for Dispersed Uranium-Plutonium Mixed Fuel	1
Concentration of Intermediate Molybdenum Isotopes in a Cascade with a Specified Number of Gas Centrifuges in Steps	1
Neural Network Model of a Point Reactor with Feedback	1
Computational Analysis and Evaluation of the Aftereffects of Fuel Assembly Drops Using Verified Deformation Models of Structural Materials	1
Study of alkaline coolant boiling in the fuel assemblies of fast reactors in emergency modes with natural convection	1
Modes of generating pulsed discharges in chambers with inertial electrostatic plasma confinement	1
A study of the coolant flow at the inlet to the fuel assembly of the RITM nuclear icebreaker reactor	1
Assessing the durability of nuclear plant elements under high‑frequency broadband loading	1
Effect of Irradiation on the Properties of Cement Compound as a Matrix for Solidifying High-Level Waste	1
Online convergence forecast for axial xenon oscillations of the power density in VVER-1000 and -1200 reactors	1
Development of an Engineering Model of Fuel Pellet Sintering in Multi-Zone Furnaces	1
Tests of a Two-Stage Core at the KV-1 Test Facility: Physical Aspects and Results	1
Debatable issues on the derivation of the separation potential for multicomponent mixtures	1
Research of the influence of the feed solution flow rate on the uranium refining in an extraction column cascade	1
Development of a method for measuring the effective fraction of delayed neutrons using a 240Pu spontaneous fission source	1
Immobilization of chloride radioactive waste using a phosphate glass composite material	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
Development of Combined Polymeric Materials for Detecting Neutrons of Various Energies	1
Computer Simulation of Measurements of VVER-1200 Emergency Protection Efficacy	1
Technical and Economic Features of IAEA Safeguards Application at NPPs with a Fast Reactor and On-Site Fuel Cycle	1
Sources and Types of the Debris Generated During Loss-of-Coolant Accidents at WWER NPPs	1
Effects of Novovoronezh NPP-2 industrial development on the assessment of the external radiation dose to personnel	1
Characteristics of ZnS(Ag) + 6LiF Scintillator-Based Detector Used as a Neutron Dosimeter	1
Corrosion Assessment of Core Catcher Vessel Housing Over NPP Operating Period	1
Methodological Issues and Results of Experimental and Computational Studies of Critical Heat Flows in RITM-200 Reactor Fuel Assemblies for Small NPP	1

Effects of Accident-Tolerant Nuclear Fuel on NPP Economic Parameters	1
Extended one-group cross-section libraries in precision nuclide composition calculations of irradiated steel	1
Reactivity Effects of Steam Bubbles Injected into the BREST-OD-300 Reactor Core	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
Isolation of Intermediate-Mass Components of Spent Nuclear Fuel in a Direct-Flow Plasma Centrifuge	1
Thermophysical properties of VVER uranium-gadolinium fuel pellets with 6–10 wt% of gadolinium oxide	1
Fast neutron spectrometer based on a diamond sensor detector	1
Prospects of artificial intelligence in nuclear industry	1
230U Yield Measurement on 3,4He-Irradiated ThO2 Targets	1
Prospects for application of robotics and digitalization in integral critical experiments at compact assembly machines	1
Prospects of SNPPs in the electric power industry	1
Simulation of Two-Phase Flow of a Three-Component Mixture with Heat-and-Mass Transfer	1
Ignition of 4.8–12 Vol% Hydrogen Air Mixtures by Platinum-Coated Ceramic Particles	1
Experimental determination of the element release from aqueous media of spent nuclear fuel reprocessing into the gas phase under violated equipment integrity	1
Preparation for dismantling the liquid waste disposal system of MR and RFT research reactors	1
Triple Cascade Arrangement for Purifying Regenerated Uranium Hexafluoride from 232,234,236U	1
Computational analysis of a blackout accident at a decomissioned RBMK	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
Effects of the Thermal Exposure and Organosilicate Coating on the Properties of a Specialized Concrete for NPP Construction	1
Neutronics Models for Integrated Testing of Transport NPP on Land-Based Prototype Testing Facilities	1
Experimental Neutronics Investigations of Nuclear Propulsion Reactors on Prototype Test Bases	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
Measurement of the Yield of Protactinium Radioisotopes 230,232,233Pa on Irradiation of ThO2 Targets by 1,2H AND 3,4He Nuclei	1
Calculation and experimental studies for substantiating the design of BREST-OD-300 reactor sampler	0
Environmental Radiation Safety Assessment in the Control Area at Nuclear Facilities	0
Purification of Regenerated Uranium Hexafluoride from 232, 234, 236U in a Double Cascade with an Additional Feeding	0
Estimation of the Specific Activity of Iodine Release to Comply with the Base Principle of INPRO Methodology for PWR, BWR NPP	0
(α, n) Neutron Spectra on Thick Light Targets	0
Experimental Investigations of Severe Accidents at Nuclear Power Plants	0
Restoration of the Isotopic Composition of Regenerated Uranium in Ordinary and Pentastream Gas-Centrifuge Cascades	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
Thermal-hydraulic model of the heavy liquid metal coolant—steam-water mixture flow	0
Harmonization of Approaches to Evaluation of the Efficiency and Safe Operating Limits of Passive Catalytic Recombiners: System Model	0
MCU-BR Software Verification by Critical BFS-2 Stand Experiments	0
Influence of Manufactured-Part Design and Gasket Material on the Tightness of Flanged Joints Under Sharp Thermal Cycles in the Environment	0
Role of the BOR-60 research reactor in the development of fast reactors	0
Possible Distortions of Low-Temperature Monitoring of the Water Redox Potential in VVER Primary Loop	0
Optimization of spent nuclear fuel reprocessing for reducing radioactive waste	0
Use of Burnable Absorbers in the PIK Reactor to Increase the Run Time	0
Distribution of the effective dose of ionizing radiation in the central hall of the IGR reactor after startups	0
Nuclear power in accelerated economic growth scenarios	0
Neutronics Efficacy Evaluations of Lithium-Uranium and Lithium-Thorium Blankets in a Thermonuclear Plant	0
A method for design a linear heat rate ramp limit curve for thermal reactor fuel rods	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
Methodology for forming the VVER reactor parameter requirements in cycling power reactor tests	0
Neutronics Calculations of Performance Enhancement of the Lithium-Uranium Blanket of a Tokamak Reactor	0
Evaluation of the effectiveness of investments in spent nuclear fuel reprocessing	0
Methodological Basis for the Modernization of Thermal Control of NPP–VVER	0
E110-Type Zirconium Alloys – Dilatometric Determination of Solidus and Liquidus Temperatures	0
Analysis of criteria for transmutation as an effective method for removing hazardous radioactive waste	0
Gamma-Imaging for Remote Dosimetry in the Nuclear Industry	0
Modeling of the ACE-L8 Experiment on Melt–Concrete Interaction	0
BF3 for Compensation and Additional Emergency Protection in HTGR	0
Severe Accident Management at NPP-2006 Reactor Plants (Leningrad NPP-2)	0
Technologies of Np, Am Afterburning in Fast Reactors with Mixed Uranium-Plutonium Nitride Fuel	0
Experimental study of the hydrogen leakage and ignition in a ventilated room	0
Increased sensitivity of fuel cladding failure detection	0
Uncertainty Assessment and Sensitivity Analysis in the Problems of Nuclide Kinetic Modeling Using the Sun Module of BPSD Software	0
Possibility of Increasing Cyclotron Production of 123I at the NRC Kurchatov Institute	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
Reduction of the Systematic Error of the Monte Carlo Method in MCU-Aided Calculations of Nuclear Reactors	0
Development and testing of methods for extracting and conditioning accident elimination sorbents in the basements of the Fukushima Daiichi NPP	0
Correction to: Reduction of the Systematic Error of the Monte Carlo Method in MCU-Aided Calculations of Nuclear Reactors	0
Modeling of Aerodynamics and Heat-and-Mass Transfer on Ventilation of Industrial Enclosures	0
Method of Integral Reliability Assessment of Equipment and Personnel of Long-Operating NPP Power Unit	0
Cation Diffusion in a Crystallite of Mineral Illite	0
Optimal rotor length of a gas centrifuge	0
Effects of meteorological parameters on the intensity of tritium emission from spray cooling ponds	0
Effect of the Operation of a Polar Crane on the Stress-Strain State of NPP Containment	0
Gibbsite- and kuzelite-based matrix for the preservation of radioactive aqueous sodium nitrate concentrates	0
Justification of the CONV-3D code for simulating natural circulation of a lead-bismuth coolant in a hydraulic circuit	0
Development of Atomic-Hydrogen Energy Technologies in the Rosatom State Corporation	0
On the Matter of Different Approaches to a National Strategy for the Development of Nuclear Energy	0
Certain Aspects of Using 15N-Enriched Mixed Uranium-Plutonium Nitride Fuel in a Fast-Reactor Fuel Cycle	0
Accident Tolerant Fuel with Chromium-Coated Fuel-Rod Cladding	0
Features of coolant movement at the boundary of jacketless fuel assemblies with fuel rods of various diameters	0
Enthalpy and heat capacity of lead in a condensed state	0
MZK Program for Solving Stiff Systems in Nuclide Kinetics Problems	0
The Initial Stage of Closing the NFC of the Russian Two-Component Nuclear Power Engineering System	0

Purification of Alkali-Metal Chlorides by Zone Recrystallization for Use in Pyrochemical Processing of Spent Nuclear Fuel	0
Certain Problems of Lengthened Cooldown of NPP–VVER Power Units in Accidents with Loss of Primary-Loop Coolant	0
Hot Isostatic Pressing Temperature Effect on Chromium-Zirconium Copper Alloy Structure and Properties	0
Calculation of X-Ray Dose Loads in the Human Body Using Voxel Phantoms and the MCU Program	0
Adaptation of RT-1 Plant Technology to Processing of New Types of Spent Nuclear Fuel	0
Evaluation of Onboard Radiometric System for Remote Sensing Detection of Heightened Radioactivity of Soil	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
Fast reactors in the strategic nuclear power development scenarios of the Russian Federation	0
Informativity of the Status Parameters for Fuel Rod Claddings of Transport NPPs	0
Corrosion tests of triuran disilicide fuel pellets	0
Fire protection system for sodium equipment rooms of BN reactors: operating experience and development trends	0
Influence of Vertical Rib Size on UF6 Desublimation in Vertical Submersible Tanks	0
Key lessons from major radiation accidents for emergency response in agriculture	0
Techno-Economic Prognosis for the Manufacture of Fuel Assemblies with Mixed Uranium-Plutonium Fuel for the VVER-SKD Power Reactor	0
Tritium distribution between the primary circuit and associated systems of a VVER NPP power unit	0
Voloxidated Spent Nuclear Fuel Metallization: Mathematical Model	0
Evaluation of technological uncertainties using the sensitivity to nuclear data	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
Prospective Accident-Tolerant Uranium-Molybdenum Metal Fuel	0
MCU–RELAP Software Package for Analyzing Accidents and Non-Stationary Processes in the PIK Reactor	0
Investigation of the Operating Regimes of Penning Ion Sources in Inhomogeneous Magnetic Fields	0
Computational-Theoretical Investigations of Thermophysical and Physicochemical Processes Occurring During Severe Accidents at NPP–VVER	0
Aerodynamic model based on similarity numbers and computational fluid dynamics for coolant mixing in HTGR bottom plenum	0
Development of approaches to regulatory safety in industrial water-electrolysis production of hydrogen at NPPs	0
Change of Interatomic Forces in Metal Under the Action Of Ionizing Radiation	0
Assessment of the state of water bodies in the territory of a decommissioned uranium mining enterprise	0
Increasing the operational stability of a vacuum neutron tube ion source	0
Prospects for fusion neutron sources in the Russian nuclear power industry	0
Decommissioning of fuel elements at the reactor of the “Akademik Lomonosov” floating thermal power plant	0
Spectral Analysis in Neutron Distribution Problems in Weakly Coupled Systems	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
Methods for Estimating a Neutron Spectrum Using a Diamond Detector, Plastic Scintillator, and Set of Activation Detectors	0
Short-Time Mechanical Properties of EP823-SH Ferrite-Martensite Steel After High-Dose Neutron Irradiation	0
Use of a refueling machine mast sipping system to detect leaking FAs during operational fuel cladding failure detection	0
Technical and economic aspects of a nuclear power engineering plant for hydrogen production	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
Experimental and computational-theoretical capabilities of RFNC—VNIITF and the tasks of ensuring the safety of hydrogen energy technologies	0
Analysis of Gamma-Radiation Background Changes During Periods of Atmospheric Precipitation	0
Magnesium potassium phosphate matrix for solidification of a spent tributyl phosphate—dodecane simulant	0
Results of BOR-60 reactor tests and post-reactor studies of experimental fuel rods with mixed uranium-plutonium nitride fuel	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
Transport-NPP Secondary-Loop Water-Chemistry Management Based on Ion-Exchange Sorbent Analysis	0
First Cryogenic Tests of Superfluid Helium Heat Exchanger for an Ultracold Neutron Source	0
Environmental Risk Analysis of Radioactive Contamination of the Ol’khovskoe Marsh	0
Liquid Radwaste Denitration by Electrochemical Reduction of Nitric Acid	0
Calculation of a squared-off cascade for simultaneous concentration of intermediate components	0
Calculation and experimental analysis of BN-800 neutron-physical characteristics during the transition to mixed oxide fuel loading	0
Coolant nuclid kinetics for fast reactors	0
Parametric Model of the Production Process of Radiopharmaceuticals	0
Neutron generators with an external target at the remote end of the neutron tube ion guide	0
Modeling of the Dynamics of Plasma Flows and Neutron Generation in a Portable Generator with a Laser-Plasma Ion Diode	0
Investigation of Fission Product Release from Irradiated Oxide and Nitride Nuclear Fuel on High-Temperature Heating in Helium Flow	0
Method of Calculating and Optimizing Multiflow Cascades for Separating Multicomponent Isotopic Mixtures	0
Validation of the EUCLID/V1 integrated computer code against the BOR-60 experimental data	0
What Can and Cannot Be Expected from Tokamak Fusion	0
Low-Pressure Nanofiltration Systems for Decreasing Boric Acid Ingress Into Drain Water in NPP with VVER	0
Radon Flux Density Measurement on Rock Surfaces	0
R&D Test Bench for Investigating the Dynamic Adsorption of Radon from Airflows	0
Validation of the steam generator model in the RASNAR-GAZ software for calculating the dynamics of a gas-cooled reactor plant	0
Method for Determining and Transmitting Data on Radioactive Contamination of the Sea-Bottom in Deep-Water Areas	0
Calculation of Multistage Schemes for Concentrating Isotopes in a Gas-Centrifuge Cascade with Variable Separation Factors	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
Application of metal-ceramic uranium-molybdenum fuel in an aluminum matrix for research reactors	0
Calculation analysis of a severe accident at a nuclear power plant with a sodium-cooled fast reactor	0
Self-protection of fast lead-cooled reactors against the partial blockage of the core flow area	0
Radiation and Radiological Consequences of a Hypothetical Nuclear Accident at a Nuclear Facility Located in the Positional-Home District of Atomflot	0
Radionuclides in the Soil of Typical Arctic Tundra and Beneath a Bird Colony Near the Russian Village of Barentsburg (Svalbard Archipelago)	0
New challenges for the steam-power cycle in power plants based on lead-cooled reactors	0
Nitriding and Carburization of a Mixed Nitride Uranium-Plutonium Fuel Pin Cladding	0
Reduction of the erbium content in RBMK-1000 fuel	0
Analytical simulation of sustainable development scenarios for global two-component nuclear power industry. Part 1. Thermal reactor scenarios	0
Determination of the Fast Neutron Fluence on a VVER-1200 Vessel Using a Computational Model Including the Monte Carlo Method	0
Approaches to the Assessment of the Cost for the Construction of Innovative Nuclear Power Facilities at the Early Stages of Design	0
A comparative analysis of the consequences of accidents at Chernobyl and Fukushima Daiichi (Japan) NPPs for agriculture and the environment	0
Release of radioactive cesium to the environment during standard npp operations	0
BM-U facility for simulating emergency processes involving the propagation and combustion of flammable gases	0
Analysis of charged particle flows in the interelectrode gap of an ion-optical system	0
Experience of Operating VVR-K with a Beryllium Reflector and Low-Enriched Uranium Fuel	0
Formation of intermetallics during the metallization of model nuclear fuel based on uranium dioxide containing oxides of rare earth metals and palladium	0
Flow formation features at the inlet to the fuel catridge of a ritm snpp reactor	0
Dynamics of Fish Fauna Dose Loads in the Cooling-Water Reservoir of the Beloyarsk NPP	0
Immobilization of Actinide Radwaste into a Perovskite-Like Matrix by Self-Propagating High-Temperature Synthesis	0
Isotopic Mixture Properties and their Variation in the Separation Process	0
Lessons learned from the experience of operating lead-bismuth nuclear power reactors	0
The effect of charge accumulation in a dielectric under the action of bremsstrahlung with a photon energy above 1 MeV	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
Software Verification for Techno-Economic Simulation of Nuclear Energy Systems: Results and Recommendations	0
Testing of a transportation and storage container model	0
Two-cascade scheme of gas centrifuges for the purification of reprocessed uranium hexafluoride from 232, 234, 236U	0
Assessment of external radiation doses to herbage under various distribution of radionuclides in the vertical soil profile	0
Estimated Transmutation Efficiency in a Molten-Salt Burner Reactor	0
High-Temperature Behavior of Irradiated Dispersion Fuel Rods with 42KhNM-Alloy Cladding	0
Distribution and Combustion of Hydrogen and Methane Mixtures with Air in a Container with Baffles: An Investigation	0