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Neutronics Analysis on High-Temperature Gas-Cooled Pebble Bed Reactors by Coupling Monte Carlo Method and Discrete Element Method.
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- Energies (19961073), 2024, v. 17, n. 20, p. 5188, doi. 10.3390/en17205188
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Modeling and Visualization of Coolant Flow in a Fuel Rod Bundle of a Small Modular Reactor.
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- Fluids, 2024, v. 9, n. 10, p. 235, doi. 10.3390/fluids9100235
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- Article
Comparative study between step and sinusoidal temperature profiles during natural convection inside a square enclosure heated from bottom.
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- Journal of Thermal Analysis & Calorimetry, 2023, v. 148, n. 7, p. 2815, doi. 10.1007/s10973-022-11907-2
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Conceptual study of an accelerator‐driven ceramic fast reactor with long‐term operation.
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- International Journal of Energy Research, 2018, v. 42, n. 4, p. 1693, doi. 10.1002/er.3970
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Effect of the Inclusion of the Detailed Geometry of the Reactor Core on the Calculated Antineutrino Flux from a VVER-1000 Reactor.
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- JETP Letters, 2024, v. 119, n. 3, p. 158, doi. 10.1134/S0021364023604025
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Effect of Meteorological Parameters on the Cosmic Muon Flux Studied Using the Effective Generation Level Method with the DANSS Detector Data.
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- JETP Letters, 2023, v. 118, n. 3, p. 165, doi. 10.1134/S0021364023602166
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Analysis of the Results of the Neutrino-4 Experiment on the Search for the Sterile Neutrino and Comparison with Results of Other Experiments.
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- JETP Letters, 2020, v. 112, n. 4, p. 199, doi. 10.1134/S0021364020160122
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- Article
A Review of Finite Element Method Models for Nuclear Graphite Applications.
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- Archives of Computational Methods in Engineering, 2020, v. 27, n. 1, p. 331, doi. 10.1007/s11831-018-09310-y
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Core Design and Deployment Strategy of Heavy Water Cooled Sustainable Thorium Reactor.
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- Sustainability (2071-1050), 2012, v. 4, n. 8, p. 1933, doi. 10.3390/su4081933
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- Article
Life Prediction of Dry Reactor Sensor Based on Deep Neural Network.
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- Journal of Sensors, 2022, p. 1, doi. 10.1155/2022/6982950
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ONE-PHASE REACTIVE GENERATOR WITH ANNULAR WINDINGS.
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- Power & Electrical Engineering, 2007, n. 20, p. 164
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- Article
Dynamics of Energy Release in a Nuclear-Reactor Core.
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- Physics of Atomic Nuclei, 2024, v. 87, n. 4, p. 389, doi. 10.1134/S106377882470039X
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Ensuring Irradiation Conditions for Metal Specimens within a Materials Science Assembly to Validate the BN-600 Operational Life Extension.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 12, p. 2557, doi. 10.1134/S106377882310023X
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Application of Minor Actinides for the Large-Scale Production of <sup>238</sup>Pu in a Supercritical Light-Water Reactor.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 10, p. 2165, doi. 10.1134/S106377882310037X
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Beyond Design Basis Accident with Blackout of the RBMK. Analysis of the Possibility of Recriticality Occurrence.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1907, doi. 10.1134/S1063778823080082
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Thermal Stability of Nanosized Nonmetallic Phase Particles in Low-Activated Dispersion Hardening Vanadium Alloys.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 7, p. 1577, doi. 10.1134/S1063778823070220
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Antineutrino Spectra of U and Pu Taken from the Double Chooz Experiment.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 6, p. 1178, doi. 10.1134/S1063778824010599
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Measurements of the Absolute Reactor Antineutrino Energy Spectrum Dependence on the Fuel Composition.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 4, p. 544, doi. 10.1134/S1063778823040324
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Hydrogen Solubility in Zirconium Alloys E110opt and E635.
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- Physics of Atomic Nuclei, 2022, v. 85, n. 11, p. 1808, doi. 10.1134/S1063778822110060
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Development of the High-Brilliance Cold Neutron Source for HEC-2 Channel of the PIK Reactor.
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- Physics of Atomic Nuclei, 2022, v. 85, n. 9, p. 1505, doi. 10.1134/S1063778822090216
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Development of Reduced 3D Models for Neutronic Calculations of the ASTRA Critical Facility.
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- Physics of Atomic Nuclei, 2022, v. 85, n. 8, p. 1383, doi. 10.1134/S106377882208018X
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Issue of the Dynamics of the Pulsed Fast Reactor NEPTUN: Comparison of the Calculation Models.
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- Physics of Atomic Nuclei, 2022, v. 85, n. 8, p. 1299, doi. 10.1134/S1063778822080099
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Estimation of the Pure Condensate Flow Rate in the Starting Range in the Startup to the Minimum Controlled Power Level after the Activation of Emergency Protection.
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- Physics of Atomic Nuclei, 2022, v. 85, n. 8, p. 1279, doi. 10.1134/S1063778822080014
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Analysis of Methods and Technologies for Assessing the Composition of the Corium Formed as a Result of the Accident at the Fukushima Daiichi NPP.
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- Physics of Atomic Nuclei, 2022, v. 85, n. 2, p. S90, doi. 10.1134/S1063778822140125
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Test Results of Variance Reduction Techniques Applied to the Deep Penetration Problem.
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- Physics of Atomic Nuclei, 2022, v. 85, n. 2, p. S19, doi. 10.1134/S1063778822140034
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Estimates of the Flow Rate of Pure Condensate when Reactor Plant WWER-1200 is Brought to the Minimum Controlled Power Level after the Emergency Protection Triggering.
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- Physics of Atomic Nuclei, 2022, v. 85, n. 2, p. S1, doi. 10.1134/S1063778822140010
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New Antineutrino Spectra of Nuclear-Reactor Fissile Isotopes: Experiment and Calculations.
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- Physics of Atomic Nuclei, 2022, v. 85, n. 6, p. 690, doi. 10.1134/S1063778823010611
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Production of the <sup>186m</sup>Re Isomer in Nuclear Reactors.
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- Physics of Atomic Nuclei, 2021, v. 84, n. 11, p. 1817, doi. 10.1134/S1063778821090209
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Principle of Switching Power-Generating Channels in the Core of a Thermionic Reactor-Converter.
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- Physics of Atomic Nuclei, 2021, v. 84, n. 8, p. 1527, doi. 10.1134/S1063778821080032
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Results of Research of YAGUAR Reactor Characteristics after Modernization.
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- Physics of Atomic Nuclei, 2021, v. 84, n. 8, p. 1419, doi. 10.1134/S1063778821080135
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Complex Calculation of Solution Pulsed Nuclear Reactor VIR-2M.
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- Physics of Atomic Nuclei, 2021, v. 84, n. 8, p. 1459, doi. 10.1134/S1063778821080056
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Advantages of a Fast Reactor Core Surrounded by a Physically Thick Neutron Reflector Made of Lead-208.
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- Physics of Atomic Nuclei, 2020, v. 83, n. 9, p. 1291, doi. 10.1134/S1063778820090240
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New Results of Measurements in the Neutrino-4 Experiment Devoted to Searches for Sterile Neutrinos.
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- Physics of Atomic Nuclei, 2020, v. 83, n. 6, p. 930, doi. 10.1134/S1063778820060265
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Comparing Measured and Simulated Reaction Rates in Uranium and Nickel Detectors of the BARS-5M–RUN-2 Reactor Complex.
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- Physics of Atomic Nuclei, 2020, v. 83, n. 8, p. 1221, doi. 10.1134/S1063778820080104
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A Method for Calculating the Number of Fissions in the VIR-2M Reactor from Measured Yields of Fission Products.
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- Physics of Atomic Nuclei, 2020, v. 83, n. 8, p. 1216, doi. 10.1134/S1063778820080086
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Application of the Pulsed-Neutron Method for Measuring the Reactivity of the Fissile Systems with Reflector.
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- Physics of Atomic Nuclei, 2019, v. 82, n. 8, p. 1088, doi. 10.1134/S1063778819080155
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Influence of the gamma-ray fraction in the reactor radiation on the total signal of a self-powered neutron detector.
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- Physics of Atomic Nuclei, 2013, v. 76, n. 13, p. 1578, doi. 10.1134/S1063778813130061
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Full-scale mathematical model for describing the temperature conditions of a reactor of the RBMK type in the case of an accident with complete deenergization.
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- Physics of Atomic Nuclei, 2013, v. 76, n. 13, p. 1595, doi. 10.1134/S106377881313005X
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Dynamic characteristics of a VK-50 reactor operating under conditions of the loss of a normal feedwater flow.
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- Physics of Atomic Nuclei, 2013, v. 76, n. 13, p. 1601, doi. 10.1134/S1063778813130097
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Allowance for the burnup of a rhodium self-powered neutron detector in a VVER-1000 reactor.
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- Physics of Atomic Nuclei, 2013, v. 76, n. 13, p. 1586, doi. 10.1134/S1063778813130073
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The role of chemical reactions in the Chernobyl accident.
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- Physics of Atomic Nuclei, 2010, v. 73, n. 14, p. 2296, doi. 10.1134/S1063778810140073
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- Article
Event Sequence Based Fault Tree Analysis to Evaluate Minimal Combination of Event Sequences Leading to the Reactor Core Damage.
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- Gazi University Journal of Science, 2024, v. 37, n. 3, p. 1319, doi. 10.35378/gujs.1313692
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Diffraction Contrast Scanning Transmission Electron Microscopy - A Bend-contour-free Way to Image Dislocations, Voids and Precipitates.
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- Microscopy & Microanalysis, 2019, p. 1472, doi. 10.1017/S1431927618007845
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Mathematical modelling of nonlinear vibration and fretting wear of the nuclear fuel rods.
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- Archive of Applied Mechanics, 2016, v. 86, n. 4, p. 657, doi. 10.1007/s00419-015-1053-0
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- Article
Investigation of the Characteristics of Neutron Fields in Channels of a Graphite Prism and Cylindrical Moderators Near the Bars-6 Reactor Cores.
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- Measurement Techniques, 2014, v. 57, n. 4, p. 431, doi. 10.1007/s11018-014-0473-5
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Optimization of Core Regions and Fuel Fractions for Better Power Peaking Factor of 150, 450 and 1,000 MWth Molten Salt Reactor.
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- Trends in Sciences, 2023, v. 20, n. 12, p. 1, doi. 10.48048/tis.2023.6937
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- Article
Vibration detection method for core loosening degree of high‐voltage direct current converter valve saturable reactor based on variational mode decomposition‐symmetrized dot pattern and image matching.
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- IET Science, Measurement & Technology (Wiley-Blackwell), 2022, v. 16, n. 8, p. 454, doi. 10.1049/smt2.12118
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CFD Analysis of Convective Heat Transfer in a Vertical Square Sub-Channel for Laminar Flow Regime.
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- Fluids, 2022, v. 7, n. 6, p. 207, doi. 10.3390/fluids7060207
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- Article
サブチャンネルスケールの分布定数のモデル化 及びBWR 管群ボイド試験データによる妥当性確認
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- Japanese Journal of Multiphase Flow, 2021, v. 35, n. 4, p. 543
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Reactivity disturbance suppression method for small modular reactors based on core coolant flow control.
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- Scientific Reports, 2022, v. 12, n. 1, p. 1, doi. 10.1038/s41598-022-19243-z
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- Article