Contents

Physics of Atomic Nuclei


Vol. 86, No. 8, 2023


Transmission of Neutrons by a Single Crystal of Bismuth Germanate

P. P. Parshin, P. A. Borisova, V. P. Glazkov, E. V. Dyuzheva-Maltseva and V. T. Em 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

A. V. Lutsenko p. 1757  abstract

Estimation of the Effective Multiplication Factor and the Prompt Neutron Multiplication Constant for Fast Neutron Systems

L. S. Ershova and A. V. Lukin p. 1763  abstract

Determination of Energy Release from Gamma Radiation in Experimental Channels of the IR-8 Reactor

V. V. Trofimchuk, V. A. Nasonov, D. Yu. Erak, Yu. E. Pesnya, A. E. Kruglikov and O. V. Mikhin p. 1768  abstract

Analysis of Readings of Background Cores of In-Reactor Detectors

A. M. Musihin, N. V. Mil’to, A. Yu. Kurchenkov, D. N. Skorohodov, D. A. Karasev, A. I. Vereschaka and D. S. Markov p. 1778  abstract

On Conditions of Development of Neutronic Mechanisms of Instability on a Portion of Groups of Emitters of Delayed Neutrons

D. G. Kresov p. 1782  abstract

Optimal Stabilization of Reactor Power with Preliminary Identification of Its Characteristics under Conditions of Uncontrolled External Influences

A. M. Degtyarev p. 1785  abstract

Validation of ENDF/B-7.1 Library for PIK-04 Critical Experiments

M. S. Onegin 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

A. N. Pisarev and V. V. Kolesov p. 1804  abstract

KIR2 Software Complex for Simulation of a Stationary and Nonstationary Particle Transport by the Monte Carlo Method

V. I. Belousov, M. I. Gurevich, V. D. Davidenko, I. I. D’iachkov, M. V. Ioannisian, A A. Kovalishin, M. R. Malkov, K. F. Raskach, K. G. Chernov and R. V. Shirokov p. 1812  abstract

RC Code for Calculating Doses from Radioactive Releases to the Atmosphere

I. N. Geraskin, A. V. Krayushkin and A. K. Smirnova p. 1818  abstract

Calculation of the Neutronic Characteristics of a HTGR for the Verification of the MCU-HTR Software Package

A. V. Grol, V. A. Nevinitsa, P. A. Fomichenko, S. E. Sorokin and S. G. Filippov p. 1827  abstract

Computational Analysis of the Possible Location of Ionization Chambers in Fast Reactors

M. N. Zizin 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

V. Yu. Blandinsky, V. V. Kolesov, V. A. Nevinitsa, P. A. Fomichenko, A. A. Sedov, A. A. Frolov, S. B. Pustovalov, M. V. Shchurovskaya, S. S. Simonov, Yu. E. Pesnya, V. V. Trofimchuk, V. A. Nasonov and I. Yu. Zhemkov p. 1849  abstract

Evaluation of the Possibility of Using the Full Load of MOX Fuel in the VVER-600 Reactor

I. N. Trapeznikov, G. L. Ponomarenko and I. N. Vasilchenko 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

A. L. Nikolaev, M. A. Uvakin, M. V. Antipov, I. V. Makhin, E. V. Sotskov and N. V. Sharyi 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

A. V. Gurin, N. A. Kovalenko, T. D. Schepetina, S. A. Subbotin, E. A. Andrianova and I. A. Bedretdinov p. 1874  abstract

Raw Material Effect on the Characteristics of the Fission and Fusion Reactor System

E. A. Andrianova, E. V. Rodionova, T. D. Shchepetina, S. V. Tsybulsky, A. V. Gurin and N. A. Kovalenko p. 1882  abstract

Study on Minor Actinide Incineration in Molten Salt Reactors with Uranium or Plutonium Loadings

Ya. A. Kotov, V. A. Nevinitsa, O. S. Feynberg and S. V. Ignatyev p. 1887  abstract

Fuel Cycle of the LiF–BeF2 Molten Salt Actinide Burner Reactor

R. Ya. Zakirov and V. V. Ignatiev p. 1894  abstract

On Radiocarbon in Uranium Graphite Reactors

G. B. Davydova, A. V. Krayushkin and A. K. Smirnova p. 1902  abstract

Beyond Design Basis Accident with Blackout of the RBMK. Analysis of the Possibility of Recriticality Occurrence

A. V. Krayushkin and I. A. Tupotilov p. 1907  abstract

Facility for Testing MSR Materials at the NRC Kurchatov Institute

S. S. Abalin, A. M. Berezov, V. A. Zagryadskiy, V. V. Ignatiev, P. N. Ivliev, S. A. Konakov, Ya. M. Kravets, T. Yu. Malamut, V. I. Novikov, A. V. Ovcharov, I. I. Skobelin, A. I. Surenkov, I. N. Trunkin, V. N. Unezhev, O. S. Feinberg and A. V. Shinkarev p. 1914  abstract

Grain Refinement of the HAZ Metal due to Welding

A. A. Chernobaeva, D. Yu. Erak, R. O. Polyakova, O. D. Chebotaryov, Yu. E. Pesnya and V. V. Trofimchuk p. 1921  abstract

Use of Eutectic Na–Tl Coolant in a Modular Fast Reactor

P. N. Alekseev, Ia. A. Kotov and A. L. Shimkevich 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

A. V. Nikolaeva, V.V. Astakhov, A. V. Lityshev, S. I. Pantyushin and N. V. Sharyi p. 1935  abstract

Radiolysis of the Coolant during the Decomposition of a Hydrogen Solution near the Saturation Temperature in VVER Reactors

A. S. Ivanov, P. A. Kalashnikova, A. A. Kovalishin, O. Yu. Poveschenko and M. D. Taran p. 1943  abstract

Modeling the Behavior of Tritium in a Molten Salt Nuclear Reactor

P. V. Gatsa, K. A. Shutova, R. Ya. Zakirov, V. V. Ignatiev and O. S. Feynberg p. 1953  abstract