Vol. 86, No. 8, 2023
Transmission of Neutrons by a Single Crystal of Bismuth Germanate
p. 1749 abstract
Consideration of the Evolution of Limited Chains of Nuclear Fission in the Study of Probabilistic Neutron Processes in a Neutron Multiplication System
p. 1757 abstract
Estimation of the Effective Multiplication Factor and the Prompt Neutron Multiplication Constant for Fast Neutron Systems
p. 1763 abstract
Determination of Energy Release from Gamma Radiation in Experimental Channels of the IR-8 Reactor
p. 1768 abstract
Analysis of Readings of Background Cores of In-Reactor Detectors
p. 1778 abstract
On Conditions of Development of Neutronic Mechanisms of Instability on a Portion of Groups of Emitters of Delayed Neutrons
p. 1782 abstract
Optimal Stabilization of Reactor Power with Preliminary Identification of Its Characteristics under Conditions of Uncontrolled External Influences
p. 1785 abstract
Validation of ENDF/B-7.1 Library for PIK-04 Critical Experiments
p. 1795 abstract
Comparison of the Effect of Nuclear Data Uncertainty on the Accuracy of Prediction of the Isotope Composition for UO2 and MOX Fuel in Burnup Calculations for a PWR Cell
p. 1804 abstract
KIR2 Software Complex for Simulation of a Stationary and Nonstationary Particle Transport by the Monte Carlo Method
p. 1812 abstract
RC Code for Calculating Doses from Radioactive Releases to the Atmosphere
p. 1818 abstract
Calculation of the Neutronic Characteristics of a HTGR for the Verification of the MCU-HTR Software Package
p. 1827 abstract
Computational Analysis of the Possible Location of Ionization Chambers in Fast Reactors
p. 1838 abstract
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
p. 1849 abstract
Evaluation of the Possibility of Using the Full Load of MOX Fuel in the VVER-600 Reactor
p. 1856 abstract
Validation of the KORSAR/GP Code Based on the Results of Tests of Maneuvering Conditions of a VVER Reactor with an Extended Control Range
p. 1863 abstract
Analysis of Benefits and Risks of Thorium and 233U Introduction in the VVER-1200 Fuel Cycle in the Fusion-Fission Reactor System
p. 1874 abstract
Raw Material Effect on the Characteristics of the Fission and Fusion Reactor System
p. 1882 abstract
Study on Minor Actinide Incineration in Molten Salt Reactors with Uranium or Plutonium Loadings
p. 1887 abstract
Fuel Cycle of the LiF–BeF2 Molten Salt Actinide Burner Reactor
p. 1894 abstract
On Radiocarbon in Uranium Graphite Reactors
p. 1902 abstract
Beyond Design Basis Accident with Blackout of the RBMK. Analysis of the Possibility of Recriticality Occurrence
p. 1907 abstract
Facility for Testing MSR Materials at the NRC Kurchatov Institute
p. 1914 abstract
Grain Refinement of the HAZ Metal due to Welding
p. 1921 abstract
Use of Eutectic Na–Tl Coolant in a Modular Fast Reactor
p. 1928 abstract
Development of Empirical Correlations for Assessment of the Value of the Conversion Coefficient of Postulated Steam Explosion under Severe Accident at VVER Reactor Plant
p. 1935 abstract
Radiolysis of the Coolant during the Decomposition of a Hydrogen Solution near the Saturation Temperature in VVER Reactors
p. 1943 abstract
Modeling the Behavior of Tritium in a Molten Salt Nuclear Reactor
p. 1953 abstract