Transmission of Neutrons by a Single Crystal of Bismuth Germanate P. P. ParshinP. A. BorisovaV. T. Em OriginalPaper 21 February 2024 Pages: 1749 - 1756
Consideration of the Evolution of Limited Chains of Nuclear Fission in the Study of Probabilistic Neutron Processes in a Neutron Multiplication System A. V. Lutsenko OriginalPaper 21 February 2024 Pages: 1757 - 1762
Estimation of the Effective Multiplication Factor and the Prompt Neutron Multiplication Constant for Fast Neutron Systems L. S. ErshovaA. V. Lukin OriginalPaper 21 February 2024 Pages: 1763 - 1767
Determination of Energy Release from Gamma Radiation in Experimental Channels of the IR-8 Reactor V. V. TrofimchukV. A. NasonovO. V. Mikhin OriginalPaper 21 February 2024 Pages: 1768 - 1777
Analysis of Readings of Background Cores of In-Reactor Detectors A. M. MusihinN. V. Mil’toD. S. Markov OriginalPaper 21 February 2024 Pages: 1778 - 1781
On Conditions of Development of Neutronic Mechanisms of Instability on a Portion of Groups of Emitters of Delayed Neutrons D. G. Kresov OriginalPaper 21 February 2024 Pages: 1782 - 1784
Optimal Stabilization of Reactor Power with Preliminary Identification of Its Characteristics under Conditions of Uncontrolled External Influences A. M. Degtyarev OriginalPaper 21 February 2024 Pages: 1785 - 1794
Validation of ENDF/B-7.1 Library for PIK-04 Critical Experiments M. S. Onegin OriginalPaper 21 February 2024 Pages: 1795 - 1803
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 A. N. PisarevV. V. Kolesov OriginalPaper 21 February 2024 Pages: 1804 - 1811
KIR2 Software Complex for Simulation of a Stationary and Nonstationary Particle Transport by the Monte Carlo Method V. I. BelousovM. I. GurevichR. V. Shirokov OriginalPaper 21 February 2024 Pages: 1812 - 1817
RC Code for Calculating Doses from Radioactive Releases to the Atmosphere I. N. GeraskinA. V. KrayushkinA. K. Smirnova OriginalPaper 21 February 2024 Pages: 1818 - 1826
Calculation of the Neutronic Characteristics of a HTGR for the Verification of the MCU-HTR Software Package A. V. GrolV. A. NevinitsaS. G. Filippov OriginalPaper 21 February 2024 Pages: 1827 - 1837
Computational Analysis of the Possible Location of Ionization Chambers in Fast Reactors M. N. Zizin OriginalPaper 21 February 2024 Pages: 1838 - 1848
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 V. Yu. BlandinskyV. V. KolesovI. Yu. Zhemkov OriginalPaper 21 February 2024 Pages: 1849 - 1855
Evaluation of the Possibility of Using the Full Load of MOX Fuel in the VVER-600 Reactor I. N. TrapeznikovG. L. PonomarenkoI. N. Vasilchenko OriginalPaper 21 February 2024 Pages: 1856 - 1862
Validation of the KORSAR/GP Code Based on the Results of Tests of Maneuvering Conditions of a VVER Reactor with an Extended Control Range A. L. NikolaevM. A. UvakinN. V. Sharyi OriginalPaper 21 February 2024 Pages: 1863 - 1873
Analysis of Benefits and Risks of Thorium and 233U Introduction in the VVER-1200 Fuel Cycle in the Fusion-Fission Reactor System A. V. GurinN. A. KovalenkoI. A. Bedretdinov OriginalPaper 21 February 2024 Pages: 1874 - 1881
Raw Material Effect on the Characteristics of the Fission and Fusion Reactor System E. A. AndrianovaE. V. RodionovaN. A. Kovalenko OriginalPaper 21 February 2024 Pages: 1882 - 1886
Study on Minor Actinide Incineration in Molten Salt Reactors with Uranium or Plutonium Loadings Ya. A. KotovV. A. NevinitsaS. V. Ignatyev OriginalPaper 21 February 2024 Pages: 1887 - 1893
Fuel Cycle of the LiF–BeF2 Molten Salt Actinide Burner Reactor R. Ya. ZakirovV. V. Ignatiev OriginalPaper 21 February 2024 Pages: 1894 - 1901
On Radiocarbon in Uranium Graphite Reactors G. B. DavydovaA. V. KrayushkinA. K. Smirnova OriginalPaper 21 February 2024 Pages: 1902 - 1906
Beyond Design Basis Accident with Blackout of the RBMK. Analysis of the Possibility of Recriticality Occurrence A. V. KrayushkinI. A. Tupotilov OriginalPaper 21 February 2024 Pages: 1907 - 1913
Facility for Testing MSR Materials at the NRC Kurchatov Institute S. S. AbalinA. M. BerezovA. V. Shinkarev OriginalPaper 21 February 2024 Pages: 1914 - 1920
Grain Refinement of the HAZ Metal due to Welding A. A. ChernobaevaD. Yu. ErakV. V. Trofimchuk OriginalPaper 21 February 2024 Pages: 1921 - 1927
Use of Eutectic Na–Tl Coolant in a Modular Fast Reactor P. N. AlekseevIa. A. KotovA. L. Shimkevich OriginalPaper 21 February 2024 Pages: 1928 - 1934
Development of Empirical Correlations for Assessment of the Value of the Conversion Coefficient of Postulated Steam Explosion under Severe Accident at VVER Reactor Plant A. V. NikolaevaV.V. AstakhovN. V. Sharyi OriginalPaper 21 February 2024 Pages: 1935 - 1942
Radiolysis of the Coolant during the Decomposition of a Hydrogen Solution near the Saturation Temperature in VVER Reactors A. S. IvanovP. A. KalashnikovaM. D. Taran OriginalPaper 21 February 2024 Pages: 1943 - 1952
Modeling the Behavior of Tritium in a Molten Salt Nuclear Reactor P. V. GatsaK. A. ShutovaO. S. Feynberg OriginalPaper 21 February 2024 Pages: 1953 - 1963