Found: 28
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Use of Eutectic Na–Tl Coolant in a Modular Fast Reactor.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1928, doi. 10.1134/S1063778823080239
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- Article
Modeling the Behavior of Tritium in a Molten Salt Nuclear Reactor.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1953, doi. 10.1134/S1063778823080197
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- Article
Radiolysis of the Coolant during the Decomposition of a Hydrogen Solution near the Saturation Temperature in VVER Reactors.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1943, doi. 10.1134/S1063778823080070
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Development of Empirical Correlations for Assessment of the Value of the Conversion Coefficient of Postulated Steam Explosion under Severe Accident at VVER Reactor Plant.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1935, doi. 10.1134/S1063778823080264
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- Article
Grain Refinement of the HAZ Metal due to Welding.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1921, doi. 10.1134/S1063778823080021
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- Article
Facility for Testing MSR Materials at the NRC Kurchatov Institute.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1914, doi. 10.1134/S1063778823080161
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- Article
On Radiocarbon in Uranium Graphite Reactors.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1902, doi. 10.1134/S1063778823080033
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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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- Article
Fuel Cycle of the LiF–BeF<sub>2</sub> Molten Salt Actinide Burner Reactor.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1894, doi. 10.1134/S1063778823080276
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Evaluation of the Possibility of Using the Full Load of MOX Fuel in the VVER-600 Reactor.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1856, doi. 10.1134/S1063778823080148
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- Article
Computational Analysis of the Possible Location of Ionization Chambers in Fast Reactors.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1838, doi. 10.1134/S1063778823080288
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- Article
Optimal Stabilization of Reactor Power with Preliminary Identification of Its Characteristics under Conditions of Uncontrolled External Influences.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1785, doi. 10.1134/S1063778823080045
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- Article
RC Code for Calculating Doses from Radioactive Releases to the Atmosphere.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1818, doi. 10.1134/S1063778823080069
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- Article
Comparison of the Effect of Nuclear Data Uncertainty on the Accuracy of Prediction of the Isotope Composition for UO<sub>2</sub> and MOX Fuel in Burnup Calculations for a PWR Cell.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1804, doi. 10.1134/S1063778823080136
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- Article
Study on Minor Actinide Incineration in Molten Salt Reactors with Uranium or Plutonium Loadings.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1887, doi. 10.1134/S1063778823080227
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Raw Material Effect on the Characteristics of the Fission and Fusion Reactor System.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1882, doi. 10.1134/S1063778823080173
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Analysis of Benefits and Risks of Thorium and <sup>233</sup>U Introduction in the VVER-1200 Fuel Cycle in the Fusion-Fission Reactor System.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1874, doi. 10.1134/S1063778823080215
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Validation of the KORSAR/GP Code Based on the Results of Tests of Maneuvering Conditions of a VVER Reactor with an Extended Control Range.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1863, doi. 10.1134/S1063778823080252
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KIR2 Software Complex for Simulation of a Stationary and Nonstationary Particle Transport by the Monte Carlo Method.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1812, doi. 10.1134/S106377882308001X
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Peculiarities of Changes in the Isotopic Composition of Pilot Fuel Elements of a VVER-SKD Reactor under Successive Irradiation in a Fast and Thermal Neutron Spectrum.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1849, doi. 10.1134/S1063778823080185
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Validation of ENDF/B-7.1 Library for PIK-04 Critical Experiments.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1795, doi. 10.1134/S1063778823080112
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Calculation of the Neutronic Characteristics of a HTGR for the Verification of the MCU-HTR Software Package.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1827, doi. 10.1134/S1063778823080203
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On Conditions of Development of Neutronic Mechanisms of Instability on a Portion of Groups of Emitters of Delayed Neutrons.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1782, doi. 10.1134/S1063778823080094
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Analysis of Readings of Background Cores of In-Reactor Detectors.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1778, doi. 10.1134/S1063778823080240
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Determination of Energy Release from Gamma Radiation in Experimental Channels of the IR-8 Reactor.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1768, doi. 10.1134/S106377882308015X
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Consideration of the Evolution of Limited Chains of Nuclear Fission in the Study of Probabilistic Neutron Processes in a Neutron Multiplication System.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1757, doi. 10.1134/S1063778823080100
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Transmission of Neutrons by a Single Crystal of Bismuth Germanate.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1749, doi. 10.1134/S1063778823080124
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Estimation of the Effective Multiplication Factor and the Prompt Neutron Multiplication Constant for Fast Neutron Systems.
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- Physics of Atomic Nuclei, 2023, v. 86, n. 8, p. 1763, doi. 10.1134/S1063778823080057
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- Article