Atomic Energy

Article	Citations
Carbon oxides in fuel particles with uranium dioxide kernels	19
Radiometric Assessment of Nuclear Fuel Burnup in the Romashka Reactor	15
Methodological Problems in Assessing the Availability Indicators of NPP Power Units at the Design Stage	5
Experimental studies of combustion processes of stratified and uniform hydrogen-air mixtures	4
Technology development and performance study of various thermoluminescent detectors	4
Study of Effects Caused by the Neutron Value Function on Kinetic Functionals Using the MCU Software	4
Electrochemical Reduction of Uranium Dioxide in LiCl–Li2O Melt	4
Neutronic investigation of ALFRED lead-Cooled fast reactor core using monte carlo modeling	4
Laser Device for Lowering the Uranium Detection Limit in Technological Environments of NPP	4
Evaluation of the Earthworm Radiation Dose on Territory with Elevated Natural Radionuclide Content	4
Aleksandrov Research Institute of Technology – Test Base for Developing, Testing, and Investigating Different Types of Nuclear Propulsion Plants Built for Different End Uses	3
Response matrix simulation for a fast neutron spectrometer based on an organic scintillator	3
System for measuring the level and density of liquids in nuclear-safe devices for new spent nuclear fuel reprocessing facilities	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
Applicability Boron-Containing Materials Obtained by Self-Propagating High-Temperature Synthesis in Radiation Protection Technology	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
Modeling of an ACE-L4 experiment on the interaction of the melt with concrete used in the construction of VVER-1000 NPPs	3
Calculation of the Flow Parameters in the Fuel Bundles of FA with Spacers by Means of the Conv-3D Code	3
Application of laser technologies for dismantling the pipelines of MIR loop channels	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
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
Assembly of core for the IGRIK-2 solution pulse reactor	2

Demand of fusion energy for tritium and the possibility of its production in nuclear reactors	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
Critical factors of an integrated approach to the economics of small modular reactors	2
Aerosol Formation During Laser Ablation in a Magnetic Field	2
Promising Technologies for Liquid Radwaste Management in the Nuclear Industry	2
Leakage control of HTGR fuel using a weak irradiation technique	2
System for measuring low flow rates of aggressive and radioactive liquids in radiochemical industry	2
Effect of Irradiation on the Properties of Cement Compound as a Matrix for Solidifying High-Level Waste	1
Technical and Economic Features of IAEA Safeguards Application at NPPs with a Fast Reactor and On-Site Fuel Cycle	1
Development of an Engineering Model of Fuel Pellet Sintering in Multi-Zone Furnaces	1
Effects of the Thermal Exposure and Organosilicate Coating on the Properties of a Specialized Concrete for NPP Construction	1
Forecast of tritium release into the environment during the normal operation of nuclear power plants	1
Modes of generating pulsed discharges in chambers with inertial electrostatic plasma confinement	1
Assessment of the Level of Natural Circulation of VVER-1000 Coolant on the Basis of Experimental Data from the Balakovo NPP	1
Development of a method for measuring the effective fraction of delayed neutrons using a 240Pu spontaneous fission source	1
A study of the coolant flow at the inlet to the fuel assembly of the RITM nuclear icebreaker reactor	1
Computational analysis of a blackout accident at a decomissioned RBMK	1
Investigation of Plasma-Chemical Synthesis of Complex Oxide Compositions for Dispersed Uranium-Plutonium Mixed Fuel	1
Triple Cascade Arrangement for Purifying Regenerated Uranium Hexafluoride from 232,234,236U	1
Concept of Carbide Compaction of Mixed Uranium-Plutonium Fuel	1
Combined diagnostics of the technical state of mobile reflector in IBR-2 research reactor	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
Assessing the durability of nuclear plant elements under high‑frequency broadband loading	1
Simulation of the removal of radioactive aerosols from the atmosphere of NPP containment by spray system droplets using the MAVR-TA code	1
Laser Device for Monitoring NPP Level-IV Emergencies	1
Concentration of Intermediate Molybdenum Isotopes in a Cascade with a Specified Number of Gas Centrifuges in Steps	1
Prospects for application of robotics and digitalization in integral critical experiments at compact assembly machines	1
Refining the Postulated Defectiveness of NPP Equipment and Pipelines Using Bayesian Procedures	1
Effects of Accident-Tolerant Nuclear Fuel on NPP Economic Parameters	1
Concentration of Tellurium Isotopes by a Multistage Scheme in an Ordinary Cascade of Gas Centrifuges	1
Debatable issues on the derivation of the separation potential for multicomponent mixtures	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
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
Concentration of 95–97Mo and production of isotopically modified molybdenum in a multi-step scheme of a square cascade	1
Computational Analysis and Evaluation of the Aftereffects of Fuel Assembly Drops Using Verified Deformation Models of Structural Materials	1
Neural Network Model of a Point Reactor with Feedback	1
Extended one-group cross-section libraries in precision nuclide composition calculations of irradiated steel	1
230U Yield Measurement on 3,4He-Irradiated ThO2 Targets	1
Testing of sodium-heated steam generator models at SSC RF-IPPE: from BN-350 to BN-1200	1
Construction of a Theory of an Ideal Multicomponent Separating Cascade	1
Immobilization of chloride radioactive waste using a phosphate glass composite material	1
Computer simulator for training students to control the dissolution process of the nuclear fuel cycle	1
Approaches to slowing down the kinetics of a fast reactor as a means of enhancing its self-protection properties	1
Computer Simulation of Measurements of VVER-1200 Emergency Protection Efficacy	1
Detection of Indications of Nuclear Non-Proliferation Breaches By States Importing Fast Reactors with Closed NFC Installations	1
Sources and Types of the Debris Generated During Loss-of-Coolant Accidents at WWER NPPs	1
Experimental determination of the element release from aqueous media of spent nuclear fuel reprocessing into the gas phase under violated equipment integrity	1
Model-Measuring Approach to Improving Aerosol Radiation Safety Validation Mechanisms	1

Engineering and physical design of a molten salt reactor for transmutation of Np, Am, and Cm from spent VVER fuel	1
ANN-based mathematical model for improving the accuracy of liquid flow measurements at nuclear power plants	1
Flow Simulation in Direct-Flow Gas Centrifuges	1
A promising method for zinc injection into the coolant of water-cooled nuclear reactors	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
Optimization of Two- and Three-Cascade Schemes for Efficient Separation of Stable Isotopes	1
Development of a neural-network methodology for the safety justification of VVER reactors in manoeuvring modes	1
Study of alkaline coolant boiling in the fuel assemblies of fast reactors in emergency modes with natural convection	1
Isolation of Intermediate-Mass Components of Spent Nuclear Fuel in a Direct-Flow Plasma Centrifuge	1
Prospects of artificial intelligence in nuclear industry	1
Chemical control of coolants in heavy-water systems of a PIK reactor	1
Characteristics of ZnS(Ag) + 6LiF Scintillator-Based Detector Used as a Neutron Dosimeter	1
Neutronics Models for Integrated Testing of Transport NPP on Land-Based Prototype Testing Facilities	1
Fast reactors with lead-bismuth and lead coolants	1
Thermophysical properties of VVER uranium-gadolinium fuel pellets with 6–10 wt% of gadolinium oxide	1
Experience of Operating an Integrated Selective-Sorption Liquid-Radwaste Reprocessing Plant at SRC Zvezdochka	1
Preparation for dismantling the liquid waste disposal system of MR and RFT research reactors	1
Ignition of 4.8–12 Vol% Hydrogen Air Mixtures by Platinum-Coated Ceramic Particles	1
Background for substantiating the 80-year service life of a commercial sodium-cooled fast reactor plant	1
Development of Combined Polymeric Materials for Detecting Neutrons of Various Energies	1
Fast neutron spectrometer based on a diamond sensor detector	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
Measurement of the Yield of Protactinium Radioisotopes 230,232,233Pa on Irradiation of ThO2 Targets by 1,2H AND 3,4He Nuclei	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
Corrosion Assessment of Core Catcher Vessel Housing Over NPP Operating Period	1
Prospects of SNPPs in the electric power industry	1
Improving the efficiency of a BREST-300 NPP using the thermal energy of natural gas	1
Research of the influence of the feed solution flow rate on the uranium refining in an extraction column cascade	1
Experience of Operating VVR-K with a Beryllium Reflector and Low-Enriched Uranium Fuel	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
Flow formation features at the inlet to the fuel catridge of a ritm snpp reactor	0
High-Temperature Behavior of Irradiated Dispersion Fuel Rods with 42KhNM-Alloy Cladding	0
Methodology for forming the VVER reactor parameter requirements in cycling power reactor tests	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
Effect of the Operation of a Polar Crane on the Stress-Strain State of NPP Containment	0
Lessons learned from the experience of operating lead-bismuth nuclear power reactors	0
Thermophysical properties of VVER uranium-gadolinium fuel pellets with 3.35, 5, and 8 wt % gadolinium oxide	0
MCU–RELAP Software Package for Analyzing Accidents and Non-Stationary Processes in the PIK Reactor	0
Prospects for fusion neutron sources in the Russian nuclear power industry	0
Method of Calculating and Optimizing Multiflow Cascades for Separating Multicomponent Isotopic Mixtures	0
Testing of a transportation and storage container model	0
Possible Distortions of Low-Temperature Monitoring of the Water Redox Potential in VVER Primary Loop	0
Radon Flux Density Measurement on Rock Surfaces	0
Development of Atomic-Hydrogen Energy Technologies in the Rosatom State Corporation	0
Validation of the steam generator model in the RASNAR-GAZ software for calculating the dynamics of a gas-cooled reactor plant	0
Low-Pressure Nanofiltration Systems for Decreasing Boric Acid Ingress Into Drain Water in NPP with VVER	0
Corrosion tests of triuran disilicide fuel pellets	0
Short-Time Mechanical Properties of EP823-SH Ferrite-Martensite Steel After High-Dose Neutron Irradiation	0
The Initial Stage of Closing the NFC of the Russian Two-Component Nuclear Power Engineering System	0
Correction to: Reduction of the Systematic Error of the Monte Carlo Method in MCU-Aided Calculations of Nuclear Reactors	0
Coolant nuclid kinetics for fast reactors	0
Analytical simulation of sustainable development scenarios for global two-component nuclear power industry. Part 1. Thermal reactor scenarios	0
Development outlook for the reactor experimental base of the JSC “INM” after 2040	0
Technologies of Np, Am Afterburning in Fast Reactors with Mixed Uranium-Plutonium Nitride Fuel	0
Release of radioactive cesium to the environment during standard npp operations	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
Possibility of Increasing Cyclotron Production of 123I at the NRC Kurchatov Institute	0
Spectral Analysis in Neutron Distribution Problems in Weakly Coupled Systems	0
Prospects of using neutron beams for gamma-resonance spectroscopy	0
Two-cascade scheme of gas centrifuges for the purification of reprocessed uranium hexafluoride from 232, 234, 236U	0
Optimization of spent nuclear fuel reprocessing for reducing radioactive waste	0
Nitriding and Carburization of a Mixed Nitride Uranium-Plutonium Fuel Pin Cladding	0
Neutronics Efficacy Evaluations of Lithium-Uranium and Lithium-Thorium Blankets in a Thermonuclear Plant	0
Purification of Alkali-Metal Chlorides by Zone Recrystallization for Use in Pyrochemical Processing of Spent Nuclear Fuel	0
Radionuclides in the Soil of Typical Arctic Tundra and Beneath a Bird Colony Near the Russian Village of Barentsburg (Svalbard Archipelago)	0
Optimal rotor length of a gas centrifuge	0
Evaluation of the effectiveness of investments in spent nuclear fuel reprocessing	0
Parametric Model of the Production Process of Radiopharmaceuticals	0
Modeling of the Dynamics of Plasma Flows and Neutron Generation in a Portable Generator with a Laser-Plasma Ion Diode	0
Reduction of the erbium content in RBMK-1000 fuel	0
Justification of the CONV-3D code for simulating natural circulation of a lead-bismuth coolant in a hydraulic circuit	0
The role and position of HTGR reactor technology in the development of the Russian energy	0
Environmental Risk Analysis of Radioactive Contamination of the Ol’khovskoe Marsh	0
Methodological Basis for the Modernization of Thermal Control of NPP–VVER	0
Development of approaches to regulatory safety in industrial water-electrolysis production of hydrogen at NPPs	0
Features of coolant movement at the boundary of jacketless fuel assemblies with fuel rods of various diameters	0
Evaluation of Onboard Radiometric System for Remote Sensing Detection of Heightened Radioactivity of Soil	0
A method for design a linear heat rate ramp limit curve for thermal reactor fuel rods	0

Use of Burnable Absorbers in the PIK Reactor to Increase the Run Time	0
A comparative analysis of the consequences of accidents at Chernobyl and Fukushima Daiichi (Japan) NPPs for agriculture and the environment	0
Software Verification for Techno-Economic Simulation of Nuclear Energy Systems: Results and Recommendations	0
Development and testing of methods for extracting and conditioning accident elimination sorbents in the basements of the Fukushima Daiichi NPP	0
Scientific and technical aspects of developing a RITM-200N innovative reactor for SNPPs	0
Estimation of the maximum mass of graphite removed during phased work on the management of RBMK-1000 resource characteristics	0
Methods for Estimating a Neutron Spectrum Using a Diamond Detector, Plastic Scintillator, and Set of Activation Detectors	0
Isotopic Mixture Properties and their Variation in the Separation Process	0
Cation Diffusion in a Crystallite of Mineral Illite	0
Adaptation of RT-1 Plant Technology to Processing of New Types of Spent Nuclear Fuel	0
Calculation and experimental analysis of BN-800 neutron-physical characteristics during the transition to mixed oxide fuel loading	0
Aerodynamic model based on similarity numbers and computational fluid dynamics for coolant mixing in HTGR bottom plenum	0
Influence of Manufactured-Part Design and Gasket Material on the Tightness of Flanged Joints Under Sharp Thermal Cycles in the Environment	0
Pilot testing of chemical absorbers for protection units of vacuum pumps in collectors of a condensation-evaporation unit at a separation plant	0
Calculation model for separating a mixture of plutonium, americium, and curium in NaCl–2CsCl melt	0
Natural Suppression of Lif–Naf–Kf Corrosion Activity in a Liquid Salt Reactor	0
Development and demonstration of basics for plasma reprocessing of spent nuclear fuel	0
Liquid Radwaste Denitration by Electrochemical Reduction of Nitric Acid	0
Strength study of composite materials with boron-containing filler for neutron shielding	0
First Cryogenic Tests of Superfluid Helium Heat Exchanger for an Ultracold Neutron Source	0
New challenges for the steam-power cycle in power plants based on lead-cooled reactors	0
Neutron generators with an external target at the remote end of the neutron tube ion guide	0
Reduction of the Systematic Error of the Monte Carlo Method in MCU-Aided Calculations of Nuclear Reactors	0
Restoration of the Isotopic Composition of Regenerated Uranium in Ordinary and Pentastream Gas-Centrifuge Cascades	0
BF3 for Compensation and Additional Emergency Protection in HTGR	0
Purification of alkaline liquid high-level radioactive waste from cesium using Fersal-MD sorbent	0
Increasing the operational stability of a vacuum neutron tube ion source	0
Decommissioning of fuel elements at the reactor of the “Akademik Lomonosov” floating thermal power plant	0
Distribution and Combustion of Hydrogen and Methane Mixtures with Air in a Container with Baffles: An Investigation	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
Validation of the EUCLID/V1 integrated computer code against the BOR-60 experimental data	0
Change of Interatomic Forces in Metal Under the Action Of Ionizing Radiation	0
Gamma-Imaging for Remote Dosimetry in the Nuclear Industry	0
Results of BOR-60 reactor tests and post-reactor studies of experimental fuel rods with mixed uranium-plutonium nitride fuel	0
Technical and economic aspects of a nuclear power engineering plant for hydrogen production	0
Voloxidated Spent Nuclear Fuel Metallization: Mathematical Model	0
Heterogeneous burning of americium and neptunium in the core of a BN-1200 reactor	0
E110-Type Zirconium Alloys – Dilatometric Determination of Solidus and Liquidus Temperatures	0
Magnesium potassium phosphate matrix for solidification of a spent tributyl phosphate—dodecane simulant	0
Determination of the Fast Neutron Fluence on a VVER-1200 Vessel Using a Computational Model Including the Monte Carlo Method	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
Allowing for a Shift of an Absorbing Element Relative to a Node of the Regular Lattice in Reactor Calculations by the Hetergeneous Method	0
Modeling of the ACE-L8 Experiment on Melt–Concrete Interaction	0
Transport-NPP Secondary-Loop Water-Chemistry Management Based on Ion-Exchange Sorbent Analysis	0
Role of the BOR-60 research reactor in the development of fast reactors	0
Purification of Regenerated Uranium Hexafluoride from 232, 234, 236U in a Double Cascade with an Additional Feeding	0
Effects of meteorological parameters on the intensity of tritium emission from spray cooling ponds	0
Key lessons from major radiation accidents for emergency response in agriculture	0
Thermal-hydraulic model of the heavy liquid metal coolant—steam-water mixture flow	0
Fiber-optic sensor for long-term remote monitoring of γ-radiation at nuclear power facilities	0
Application of metal-ceramic uranium-molybdenum fuel in an aluminum matrix for research reactors	0
Comparative analysis of thermal hydraulics in once-through steam-generating channels of helical and straight tubes	0
Experimental and computational-theoretical capabilities of RFNC—VNIITF and the tasks of ensuring the safety of hydrogen energy technologies	0
Use of a refueling machine mast sipping system to detect leaking FAs during operational fuel cladding failure detection	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 and Radiological Consequences of a Hypothetical Nuclear Accident at a Nuclear Facility Located in the Positional-Home District of Atomflot	0
Immobilization of Actinide Radwaste into a Perovskite-Like Matrix by Self-Propagating High-Temperature Synthesis	0
Computational-Theoretical Investigations of Thermophysical and Physicochemical Processes Occurring During Severe Accidents at NPP–VVER	0
Influence of Vertical Rib Size on UF6 Desublimation in Vertical Submersible Tanks	0
Calculation of Multistage Schemes for Concentrating Isotopes in a Gas-Centrifuge Cascade with Variable Separation Factors	0
Increased sensitivity of fuel cladding failure detection	0
Estimated Transmutation Efficiency in a Molten-Salt Burner Reactor	0
Informativity of the Status Parameters for Fuel Rod Claddings of Transport NPPs	0
Method for utilizing contaminated fractions of reprocessed uranium enrichment in double cascade schemes	0
Uncertainty Assessment and Sensitivity Analysis in the Problems of Nuclide Kinetic Modeling Using the Sun Module of BPSD Software	0
Nuclear power in accelerated economic growth scenarios	0
Estimation of the Specific Activity of Iodine Release to Comply with the Base Principle of INPRO Methodology for PWR, BWR NPP	0
Harmonization of Approaches to Evaluation of the Efficiency and Safe Operating Limits of Passive Catalytic Recombiners: System Model	0
Enthalpy and heat capacity of lead in a condensed state	0
Analysis of criteria for transmutation as an effective method for removing hazardous radioactive waste	0
Gibbsite- and kuzelite-based matrix for the preservation of radioactive aqueous sodium nitrate concentrates	0
Approaches to the Assessment of the Cost for the Construction of Innovative Nuclear Power Facilities at the Early Stages of Design	0
Calculation of X-Ray Dose Loads in the Human Body Using Voxel Phantoms and the MCU Program	0
Hot Isostatic Pressing Temperature Effect on Chromium-Zirconium Copper Alloy Structure and Properties	0
Certain Aspects of Using 15N-Enriched Mixed Uranium-Plutonium Nitride Fuel in a Fast-Reactor Fuel Cycle	0
Analysis of charged particle flows in the interelectrode gap of an ion-optical system	0
Tritium distribution between the primary circuit and associated systems of a VVER NPP power unit	0
Formation of intermetallics during the metallization of model nuclear fuel based on uranium dioxide containing oxides of rare earth metals and palladium	0
Dynamics of Fish Fauna Dose Loads in the Cooling-Water Reservoir of the Beloyarsk NPP	0
Assessment of the state of water bodies in the territory of a decommissioned uranium mining enterprise	0
Calculation of a squared-off cascade for simultaneous concentration of intermediate components	0
Swelling of Intermetallic Uranium–Silumin Dispersion Fuel Composition in Experimental Fuel Rods of the SM Reactor	0
The effect of charge accumulation in a dielectric under the action of bremsstrahlung with a photon energy above 1 MeV	0
Self-protection of fast lead-cooled reactors against the partial blockage of the core flow area	0
Fire protection system for sodium equipment rooms of BN reactors: operating experience and development trends	0
Experimental Investigations of Severe Accidents at Nuclear Power Plants	0
Investigation of the Operating Regimes of Penning Ion Sources in Inhomogeneous Magnetic Fields	0
Assessment of external radiation doses to herbage under various distribution of radionuclides in the vertical soil profile	0
Severe Accident Management at NPP-2006 Reactor Plants (Leningrad NPP-2)	0
On the Matter of Different Approaches to a National Strategy for the Development of Nuclear Energy	0
Evaluation of technological uncertainties using the sensitivity to nuclear data	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
Calculation and experimental studies for substantiating the design of BREST-OD-300 reactor sampler	0
BM-U facility for simulating emergency processes involving the propagation and combustion of flammable gases	0
MZK Program for Solving Stiff Systems in Nuclide Kinetics Problems	0