Atomic Energy

Article	Citations
Brest Lead-Cooled Fast Reactor: From Concept to Technological Implementation	19
The World’s First Floating NPP: Origination and Direction of Future Development	15
Purification of Alkali-Metal Chlorides by Zone Recrystallization for Use in Pyrochemical Processing of Spent Nuclear Fuel	13
Reactor Installations for Nuclear Icebreakers: Origination Experience and Current Status	9
Spent Nuclear Fuel Reprocessing and Nuclear Materials Recycling in Two-Component Nuclear Energy	9
Features of Radiation Swelling of Uranium-Plutonium Nitride Fuel in Experimental Fuel Rods with Helium and Lead Sublayer	8
(α, n) Neutron Spectra on Thick Light Targets	7
Development of New Construction Materials for Innovative Reactor Installation Designs	7
Environmental Radiation Safety Assessment in the Control Area at Nuclear Facilities	6
Electrochemical Reduction of Uranium Dioxide in LiCl–Li2O Melt	6
Concept of a New High-Flux Periodic-Pulse Source of Neutrons Based on Neptunium	5
Production of a Short-Lived Therapeutic α-Emitter 149Tb by Irradiation of Europium by 63 MeV α-Particles	5
Role of NPPs in the Russian Electricity Industry Taking into Account Carbon Emissions Limits	5
Competitiveness Assessment of Regenerated Uranium-Plutonium Remix Fuel in Thermal Reactors	5
OKBM Afrikantov Experience in Developing Methods and Computer Codes for Reliability Analysis and Probabilistic Safety Analysis of Nuclear Installations	5
Criteria for Optimizing Technical Solutions for NPP	4
Reactor Installations with Sodium-Cooled Fast Reactors for Two-Component Nuclear Energy	4
Methodological Issues and Results of Experimental and Computational Studies of Critical Heat Flows in RITM-200 Reactor Fuel Assemblies for Small NPP	4
Phase Diagram of the Quasibinary System LiF–NaF–KF–CeF3	4
Reactor with Circulating Fuel Based on Molten Metal Fluorides for Np, Am, Cm Incineration	4
VVER-1200 Tests in No. 6 Unit of the Novovoronezh NPP During Operation in a Daily Load Schedule	4
Measurement of 186W(4He, p3n)186Re, 186W(4He, pn)188Re, 186W(4He, p)189Re Reaction Cross Sections By 4He Irradiation of 186W TARGET	4
Nuclear Ship Reactor Installations: From Gen 1 to 5	4
Calculation of a Cascade System for the Purification of Regenerated Uranium Hexafluoride from 232,234,236U	3
Promising Technologies for Liquid Radwaste Management in the Nuclear Industry	3

Damaging Factors of a Nuclear Accident at the Nuclear Submarine K-431 in the Chazhma Bay	3
Analysis of Gamma-Radiation Background Changes During Periods of Atmospheric Precipitation	3
Post-Reactor Studies of Fuel Rods with Uranium-Plutonium Nitride Fuel with Gas and Liquid-Metal Sublayer	3
Ignition of 4.8–12 Vol% Hydrogen Air Mixtures by Platinum-Coated Ceramic Particles	3
Fission Gas Release from Irradiated Uranium-Plutonium Nitride Fuel	3
Investigation of the Corrosion Resistance of Nickel-Molybdenum Alloys in the Eutectic LiF–NaF–KF	3
MZK Program for Solving Stiff Systems in Nuclide Kinetics Problems	2
Refueling System for Fast Reactors: Creation and Development	2
Neutronics Efficacy Evaluations of Lithium-Uranium and Lithium-Thorium Blankets in a Thermonuclear Plant	2
HTGR – New Prospects for Nuclear Energy	2
Conditions for Reaching Radiation Equivalence of Native Raw Materials and Long-Lived Radioactive Waste in Nuclear Energy in Russia	2
Cation Diffusion in a Crystallite of Mineral Illite	2
On the Matter of Different Approaches to a National Strategy for the Development of Nuclear Energy	2
Laser Device for Lowering the Uranium Detection Limit in Technological Environments of NPP	2
Experience of Operating VVR-K with a Beryllium Reflector and Low-Enriched Uranium Fuel	2
Nature of the Luminescence of SNC Steatite Ceramic	2
Patient Radiation Dose from Medical Diagnostic Imaging Procedures in 2018	2
Short-Time Mechanical Properties of EP823-SH Ferrite-Martensite Steel After High-Dose Neutron Irradiation	2
Fuel for VVER and PWR: Current Status and Prospects	2
Modeling of Gas-Phase Transport in Heavy Liquid-Metal Coolant Flow in the HYDRA-IBRAE/LM Thermohydraulic Code	2
Actual Developmental Problems of Small Energy Installations: SNPP Based on the SHELF-M Reactor Installation	2
Harmonization of Approaches to Evaluation of the Efficiency and Safe Operating Limits of Passive Catalytic Recombiners: System Model	2
Effect of Irradiation on the Properties of Cement Compound as a Matrix for Solidifying High-Level Waste	2
Calculation and Experimental Determination of the Neutronics Characteristics of the IRT-T Research Reactor	2
The Initial Stage of Closing the NFC of the Russian Two-Component Nuclear Power Engineering System	2
Development of a Large-Sized Highly Sensitive Detector Based on α-Si–p-i-n Heterostructures for Radonometers	2
Radiation Safety Validation of a BREST-OD-300 Installation	1
Validation of a Module Based on the Les and DNS Approximations for Simulating Single-Phase Liquid-Metal Coolant Flow in Round Pipes	1
Simulation of Two-Phase Flow of a Three-Component Mixture with Heat-and-Mass Transfer	1
Assessment of the Influence of BN-800 Operation on the Radioecological Situation in the Vicinity of Beloyarsk NPP	1
Restoration of the Isotopic Composition of Regenerated Uranium in Ordinary and Pentastream Gas-Centrifuge Cascades	1
Influence of Acting Factors on the Thermal and Stress State of the Geological Structure of a Deep Burial Site for Radwaste	1
NFC Russia Infrastructure Readiness Assessment for Development of PSKD-600 Power Reactors	1
Environmental Risk Analysis of Radioactive Contamination of the Ol’khovskoe Marsh	1
Fast Reactor Aided Adjustment of Plutonium Isotope Composition	1
Neutron-Value Function Influence on the Accuracy of MCU-Aided Calculations of the Effective Delayed-Neutron Fraction and Prompt-Neutron Generation Time: An Investigation	1
Construction of a Theory of an Ideal Multicomponent Separating Cascade	1
Experimental Investigations of Coolant Mixing in TVSA with Intensifier-Grids	1
Gas Centrifuge Cascade for Concentrating 235U in Additional Product and Purification of Processed Uranium Hexafluoride from 232,234,236U	1
New Stage in Russia’s Nuclear Energy Strategy	1
Distribution and Combustion of Hydrogen and Methane Mixtures with Air in a Container with Baffles: An Investigation	1
Testing of Dispersion Type Fuel Rods with a Heat-Proof Meat with Controlled Porosity for Small Nuclear Power Plants	1
Experimental Investigations of Severe Accidents at Nuclear Power Plants	1
Concentration of Tellurium Isotopes by a Multistage Scheme in an Ordinary Cascade of Gas Centrifuges	1
Features of americium transmutation in a BN-1200M fast reactor	1
Corrosion Resistance of Siliconized Graphite Based Structural Materials Under Decontamination Conditions	1
Radionuclides in the Soil of Typical Arctic Tundra and Beneath a Bird Colony Near the Russian Village of Barentsburg (Svalbard Archipelago)	1
Prospective Accident-Tolerant Uranium-Molybdenum Metal Fuel	1
Development and Verification of 60Co Accrual Calculation and Management Methodology	1
One-Group Cross-Sections of High-Threshold Reactions for Precision Neutronics Calculations	1

Study of the Technical Characteristics of Low-Enriched Uranium Hexafluoride in Long-Time Storage	1
Calculation of a System for Forming a Bremsstrahlung Beam in Discretely Falling Magnetic Field	1
Thermohydraulic Calculation of VVER and SCWR Reactor Channels	1
Approaches to the Assessment of the Cost for the Construction of Innovative Nuclear Power Facilities at the Early Stages of Design	1
Software Verification for Techno-Economic Simulation of Nuclear Energy Systems: Results and Recommendations	1
Methodology for Evaluating NPP Economic Indicators Including Safety	1
Maintaining and Improving the Accuracy of Feed-Water Flow Measurement and Thermal Power Determination in NPP Reactor Units	1
Detection of Indications of Nuclear Non-Proliferation Breaches By States Importing Fast Reactors with Closed NFC Installations	1
Applicability Boron-Containing Materials Obtained by Self-Propagating High-Temperature Synthesis in Radiation Protection Technology	1
Method of Calculating and Optimizing Multiflow Cascades for Separating Multicomponent Isotopic Mixtures	1
Supercomputer Twin of a Nuclear Energy Installation: Developmental Approaches and Application Experience	1
Level-3 Probabilistic Safety Analysis for NPP Siting Decisions	1
Utilization of spent nuclear fuel and transuranic actinides in a two-component nuclear power industry	1
42KhNM Alloy and Silicon Carbide as Material for Accident-Tolerant Fuel-Rod Cladding	1
Development of Atomic-Hydrogen Energy Technologies in the Rosatom State Corporation	1
Accident Tolerant Fuel with Chromium-Coated Fuel-Rod Cladding	1
Determination of 137Cs Radioactive Contamination over Soil Depth Using a Xenon Spectrometer	1
Modeling of the ACE-L8 Experiment on Melt–Concrete Interaction	1
Optimization of Two- and Three-Cascade Schemes for Efficient Separation of Stable Isotopes	1
Economic Efficiency of Large, Medium, and Small Size NPP Including Construction Stage Risks	1
Liquid Metal Research (History and Knowledge to be Preserved)	1
Laser Device for Monitoring NPP Level-IV Emergencies	1
Mcu-PD Code Calculation of Personnel Irradiation Dose in an Accident with Coolant Leakage in Serviced Enclosures in NPP with VVER-1000	1
High-Temperature Behavior of Irradiated Dispersion Fuel Rods with 42KhNM-Alloy Cladding	1
Method of Integral Reliability Assessment of Equipment and Personnel of Long-Operating NPP Power Unit	1
Aerosol Formation During Laser Ablation in a Magnetic Field	1
Radionuclide Composition of NPP Gas Emissions and Population Radiation Dose Assessment	1
Investigation of Methods for Separating Thorium and Rare-Earth Elements in Nitric-Acid Leaching Solutions for Loparite Concentrate	1
Development of Combined Polymeric Materials for Detecting Neutrons of Various Energies	1
Flow Simulation in Direct-Flow Gas Centrifuges	1
Nuclear Non-Proliferation Security on Exportation of Fast Reactors with a Closed Fuel Cycle	1
Computational Analysis and Evaluation of the Aftereffects of Fuel Assembly Drops Using Verified Deformation Models of Structural Materials	1
Neutronics Calculations of Performance Enhancement of the Lithium-Uranium Blanket of a Tokamak Reactor	1
Certain Aspects of Using 15N-Enriched Mixed Uranium-Plutonium Nitride Fuel in a Fast-Reactor Fuel Cycle	1
Estimation of the Specific Activity of Iodine Release to Comply with the Base Principle of INPRO Methodology for PWR, BWR NPP	1
Immobilization of Actinide Radwaste into a Perovskite-Like Matrix by Self-Propagating High-Temperature Synthesis	1
Homogenous Transmutation of 237Np, 241Am, 243Am in a Lead-Cooled Fast Reactor	1
Prospects for using Chromium-Nickel Alloy 42KhNM in Different Types of Reactors	1
Role of Nuclear Hydrogen Power Plants in Local Power Systems with Unconventional Energy Sources	1
Virtual-Digital Model of NFC Closure for a Fast Reactor	1
Investigation of Fission Product Release from Irradiated Oxide and Nitride Nuclear Fuel on High-Temperature Heating in Helium Flow	1
Investigation of Discharge Generation Regimes in Penning Ion Sources Under Pulse-Packet Control	1
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	1
Dual-Cascade Scheme with Additional Feed and Product Streams for Purification of Regenerated Uranium Hexafluoride from 232,234,236U	1
3D Modeling of NPP Containment Medium Mixing During the Development of Severe Accidents	1
Testing of Nonstationary VVER-1200 Operating Regimes in Belarusian NPP No. 1	1
Development of FA with High-Density Fuel for Foreign Research Nuclear Reactors of Russian Design	0
Separation of a Gas Mixture Containing Uranium Hexafluoride, Hydrogen Fluoride, and Chlorine Trifluoride	0
Effect of nuclear fuel composition on neutrons yield in high-energy-density plasma	0
Probabilistic Reliability Analysis of the Process Line Systems of the Fuel Fabrication/Refabrication Module of a Pilot-Demonstration Energy Complex	0
Response matrix simulation for a fast neutron spectrometer based on an organic scintillator	0
Methodological Basis for the Modernization of Thermal Control of NPP–VVER	0
Membrane-Sorption Technology for Purification and Concentration of Low-Level Liquid Waste from Transport NPPs	0
Concept of Carbide Compaction of Mixed Uranium-Plutonium Fuel	0
Calculation and experimental analysis of BN-800 neutron-physical characteristics during the transition to mixed oxide fuel loading	0
Fuel-Rod Design and Materials Validation for 10 MW NPP	0
Calculation and Justification of Biological Protection for Hot Cells with Reprocessed-99Mo Volume Enlargement at Karpov Research Institute of Physical Chemistry	0
Neutronic investigation of ALFRED lead-Cooled fast reactor core using monte carlo modeling	0
Features of Impurity Distribution in the Crystallization of Ammonium Tetrafluoroberyllate	0
MCU-BR Software Verification by Critical BFS-2 Stand Experiments	0
Aleksandrov Research Institute of Technology – Test Base for Developing, Testing, and Investigating Different Types of Nuclear Propulsion Plants Built for Different End Uses	0
Technology development and performance study of various thermoluminescent detectors	0
Radiometric Assessment of Nuclear Fuel Burnup in the Romashka Reactor	0
Parametric Model of the Production Process of Radiopharmaceuticals	0
Assessment of the Level of Natural Circulation of VVER-1000 Coolant on the Basis of Experimental Data from the Balakovo NPP	0
Fast neutron spectrometer based on a diamond sensor detector	0
Mathematical Modeling in Designing a Chain-Type Cable-Laying Machine for NPP Equipment	0
Dose Calculations for Herbaceous Plants: Comparison of Two Methods	0
Verification and Validation of a Thermohydraulics-Neutronics Software Package for Calculating Transient Regimes in Heavy-Water Reactor Installations	0
MCU–RELAP Software Package for Analyzing Accidents and Non-Stationary Processes in the PIK Reactor	0
A system for plant-wide multi-channel backup of nuclear power plant auxiliaries	0
OKBM Afrikantov Research and Testing Complex: From Creation to the Present Day	0
Isotopic Effect – Macroscopic Manifestation of the Strong Nuclear Long-Range Interaction	0
Application of laser technologies for dismantling the pipelines of MIR loop channels	0
Verification of a Mathematical Model of 12Kh18N9 Steel Deformation Under Dynamic Loading of Fuel Assemblies	0
Study of Effects Caused by the Neutron Value Function on Kinetic Functionals Using the MCU Software	0
Method for determining the realistic size of a crack in a containment in the case of a severe accident	0
Experimental studies of combustion processes of stratified and uniform hydrogen-air mixtures	0
Influence of the composition and burnup of accident-tolerant fuel on the fuel component of NPP electricity cost	0
Computer Simulation of Measurements of VVER-1200 Emergency Protection Efficacy	0

Investigation of Plasma-Chemical Synthesis of Complex Oxide Compositions for Dispersed Uranium-Plutonium Mixed Fuel	0
Refueling Complexes and Equipment for Civilian and Naval Ship Reactor Installations: Creation and Development	0
Tests of fuel elements with uranium-plutonium nitride fuel in an IGR pulsed reactor	0
Purification of Reprocessed Uranium from 232, 234U in an Additional Product with Feed Point Shifted Toward the Main Product	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
Mathematical Process-Control Model of Radioactive Waste Disposal by Self-Immersion in Geological Rocks	0
Analog Simulation of Neutron Evolution in Reactor Dynamics Problems	0
Fire simulation in the main control room of Bushehr nuclear power plant using CFAST software	0
Calculation of the Flow Parameters in the Fuel Bundles of FA with Spacers by Means of the Conv-3D Code	0
Methodology for forming the VVER reactor parameter requirements in cycling power reactor tests	0
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	0
Pumping Equipment for Nuclear Energy and the Non-Nuclear Market	0
Fuel cycles with advanced dispersion fuel elements of high uranium density	0
System for measuring the level and density of liquids in nuclear-safe devices for new spent nuclear fuel reprocessing facilities	0
Research of the influence of the feed solution flow rate on the uranium refining in an extraction column cascade	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
Certain Problems of Lengthened Cooldown of NPP–VVER Power Units in Accidents with Loss of Primary-Loop Coolant	0
Stilbene-Based Spectrometer for Unfolding the Energy Distribution of Fast Neutron Sources	0
Integral experiments with a cylindrical multiplying system of metal plutonium	0
Adaptation of RT-1 Plant Technology to Processing of New Types of Spent Nuclear Fuel	0
Enhancement of Monitoring of Condensate-Feed Systems of NPP by Analytical Composition Control of Process Waters	0
Calculated demonstration of VVER-1000 SNF actinide transmutation efficiency	0
Analysis of the Consequences of a Large Leak in a Steam Generator in a Two-Circuit Lead-Cooled Reactor Unit	0
Scientific and technical aspects of developing a RITM-200N innovative reactor for SNPPs	0
Characteristics of ZnS(Ag) + 6LiF Scintillator-Based Detector Used as a Neutron Dosimeter	0
Prospects of SNPPs in the electric power industry	0
What Can and Cannot Be Expected from Tokamak Fusion	0
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	0
Methodological Problems in Assessing the Availability Indicators of NPP Power Units at the Design Stage	0
Neural Network Model of a Point Reactor with Feedback	0
Comparative Analysis of Transmutation in a Burner Reactor Based on the Salts LiF–NaF–KF and LiF–BeF2	0
RBMK-1000 Lifespan Management and Development of Repair/Diagnostic Robotics	0
Modeling of Aerodynamics and Heat-and-Mass Transfer on Ventilation of Industrial Enclosures	0
Evaluation of the Earthworm Radiation Dose on Territory with Elevated Natural Radionuclide Content	0
Plasma Processing of Fuel Pellets	0
Arrangement of a Concrete Slab in the Backfill as a Means of Altering the Seismic Response of a Building Structure	0
Methods for Estimating a Neutron Spectrum Using a Diamond Detector, Plastic Scintillator, and Set of Activation Detectors	0
A method for design a linear heat rate ramp limit curve for thermal reactor fuel rods	0
Appraisal Method for the Population Radiation Dose from 14C Emissions of Nuclear Enterprises	0
Tests of a Two-Stage Core at the KV-1 Test Facility: Physical Aspects and Results	0
Study into the possibility of using two groups of accelerated preventive protection for VVER-1200 reactors	0
Preparation for dismantling the liquid waste disposal system of MR and RFT research reactors	0
Corrosion Assessment of Core Catcher Vessel Housing Over NPP Operating Period	0
External and internal ignition of a hydrogen-air gas mixture induced by a recombiner	0
Results of experimental testing of a hydrometallurgical technology for reprocessing spent nuclear fuel of fast neutron reactors	0
Influence of Mass Transfer and Physicochemical Processes in the Working Fluid on Erosion–Corrosion of Equipment and Pipelines in Nuclear Power Plants	0
Estimated Transmutation Efficiency in a Molten-Salt Burner Reactor	0
Numerical simulation of a hydrogen leakage in a ventilated room	0
Implementation of Parallel-Computing Algorithms for Systems with Distributed Memory in the EUKLID/V1 Integrated Computer Code	0
On the 60th anniversary of the first aperiodic pulsed nuclear reactor in Russia	0
Solution of the Equations of Nuclide Kinetics	0
Effects of Accident-Tolerant Nuclear Fuel on NPP Economic Parameters	0
Assembly of core for the IGRIK-2 solution pulse reactor	0
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	0
Estimation of the maximum mass of graphite removed during phased work on the management of RBMK-1000 resource characteristics	0
Next-Generation Capacitor-Type Nuclear Batteries with Liquid Electrolyte	0
Efficiency Assessment of Investments in Nuclear Desalination of Seawater	0
Increased sensitivity of laser monitoring of molecular iodine in the atmosphere around the location of an npp using an unmanned aerial vehicle	0
Validation of the severe accident module of the EVKLID/V2 integral code on the base of experiments with fission products release and dissociation of nitride fuel	0
Increased sensitivity of fuel cladding failure detection	0
Predictive Assessment of the Effective Dose of Irradiation of the Rural Population with Constant Radioactive Emissions from Nuclear Power Plants	0
Experimental Neutronics Investigations of Nuclear Propulsion Reactors on Prototype Test Bases	0
Purification of Regenerated Uranium Hexafluoride from 232, 234, 236U in a Double Cascade with an Additional Feeding	0
Accounting for the reference data correlation when determining the calculation error using the maximum likelihood method	0
Heat-Exchange Regularities and Thermohydraulic Code Verification for Supercritical Pressure Water Cooled Reactors	0
ANIS-V3 Measuring-and-Computing Complex	0
Experimental study of hydrodynamic stability limits in the system of parallel steam-generating channels	0
Procedure for Selecting a Variant of Dismantling and Handling of Activated Elements of a Reactor Plant During Decommissioning of NPP-VVER Units	0
Probabilistic Safety Analysis of Nuclear Installations of Different Types and Classes	0
Radiation and Radiological Consequences of a Hypothetical Nuclear Accident at a Nuclear Facility Located in the Positional-Home District of Atomflot	0
Modeling of an ACE-L4 experiment on the interaction of the melt with concrete used in the construction of VVER-1000 NPPs	0
Reactor Tests of High-Temperature Gas-Cooled Fuel Rods	0
Hot Isostatic Pressing Temperature Effect on Chromium-Zirconium Copper Alloy Structure and Properties	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
Modeling of the Dynamics of Plasma Flows and Neutron Generation in a Portable Generator with a Laser-Plasma Ion Diode	0
Use of a refueling machine mast sipping system to detect leaking FAs during operational fuel cladding failure detection	0
Reactor Pressure Vessel Cooling Scheme: Selection and Validation for Small Nuclear Power Plants	0
Radon Flux Density Measurement on Rock Surfaces	0
230U Yield Measurement on 3,4He-Irradiated ThO2 Targets	0
TERMIT technology for developing simulation systems of small nuclear power facilities	0
Sources and Types of the Debris Generated During Loss-of-Coolant Accidents at WWER NPPs	0
Conversion of CPS Channels at the Leningrad NPP Power Units 3 and 4 for the Production of Radionuclides	0
Effects of control rod movement parameters on the simulation of VVER-1200 rod ejection accidents	0
Development of a Focusing Device for Neutron Control in Nuclear Energetics	0
Experimental study of the hydrogen leakage and ignition in a ventilated room	0
Demand of fusion energy for tritium and the possibility of its production in nuclear reactors	0
New approaches to the separation and concentration of americium in high oxidation forms for the fractionation of high-level waste	0
Ordinary Gas-Centrifuge Cascades for Purifying Reprocessed Uranium Hexafluoride from 232,234U	0
Determination of the dose rate from the pulse-height spectra of an airborne gamma-ray spectrometer based on an unmanned aerial vehicle	0
Development of CPS Mechanisms for Naval and Civilian Ship Nuclear Installations	0
Use of Burnable Absorbers in the PIK Reactor to Increase the Run Time	0
Use of Nuclear Energy in Outer-Space Systems	0
Optimization of the square and squared-off cascades to separate stable isotopes using meta-heuristic algorithms	0
Computational Aspects of Core Neutronics Calculation of Sodium-Cooled Fast Reactor at the Core Destruction Stage	0
Advanced methods for laser dismantling of spent fuel assemblies and fuel rods in the primary operations of the robotic production in a closed nuclear fuel cycle	0