Contents

Physics of Atomic Nuclei

Vol. 88, No. 8, 2025

Effect of Inelastic Scattering on the Neutron Transmission by a Lead Single Crystal

P. P. Parshin, V. P. Glazkov, and E. V. Dyuzheva-Maltseva p. 1355  abstract

Development and Implementation in the KIR Code of the Method for Accounting for the Continuity of Material Density Distribution

V. I. Belousov, M. I. Gurevich, V. D. Davidenko, M. V. Ioannisian, and K. F. Raskach p. 1362  abstract

Algorithms for Calculating Effective Parameters of the Point Kinetics Equation Based on the Monte Carlo Method, Their Verification, and Validation

V. I. Belousov, E. A. Gomin, V. D. Davidenko, I. I. Dyachkov, M. V. Ioannisian, K. F. Raskach, and A. N. Pisarev p. 1369  abstract

Modification of the Frank-Kamenetsky Algorithm for Parallel Computing

V. I. Belousov, M. I. Gurevich, V. D. Davidenko, M. V. Ioannisian, K. F. Raskach, and K. G. Chernov p. 1381  abstract

On the Methodical Error of Calculation of the Jasper Radial Shield Experiment Based on DDL Schemes of the Discrete Ordinate Method for the Case of a Spherical Source

A. A. Nikolaev and A. Yu. Tarasov p. 1393  abstract

Multiphysics Analysis of Molten Salt Reactors

K. S. Kupriyanov, O. S. Feynberg, and V. V. Ignatiev p. 1399  abstract

Simulation of Neutronic Characteristics of the HTGR Core during the Fuel Cycle Using the Precision Calculation Code MCU-HTR

A. N. Lepekhin, V. Yu. Galickih, S. E. Sorokin, G. S. Filippov, A. V. Grol, M. I. Gurevich, P. A. Fomichenko, and D. A. Shkarovskiy p. 1411  abstract

Evaluation of Uncertainty in Calculations of Isotopic Composition of the Uranium–Plutonium Nitride Fuel Samples Irradiated in BN-600

O. I. Potapova, A. A. Belov, and O. N. Andrianova p. 1417  abstract

Development of a Package of Codes for Radiation Safety Analysis in Severe Accidents at NPPs with VVERs

Yu. B. Shmelkov, Yu. A. Zvonarev, and Yu. M. Semchenkov p. 1425  abstract

Numerical Study of the Efficiency of Reflooding the Heated Core of a VVER-1000 Reactor at the Beginning of a Beyond Design Basis Accident with a Large Break LOCA

I. S. Akhmedov, K. S. Dolganov, N. I. Ryzhov, D. Yu. Tomashchik, A. E. Tarasov, and A. E. Kiselev p. 1435  abstract

Sensitivity Analysis for beyond Design Basis Accidents of VVER-1200 Power Unit

M. V. Gamagin, D. S. Gordeev, S. I. Pantushin, and P. V. Yagov p. 1444  abstract

Analysis of Accidents with CPS CR Ejection at VVER Reactor Plants with Regard to Real Hydrodynamic Forces

G. A. Ryabov, A. L. Nikolaev, M. A. Uvakin, M. V. Antipov, I. V. Makhin, and N. A. Dar’in p. 1455  abstract

Features of Uncertainty Analysis for Probabilistic Safety Analysis

A. V. Nikolaeva, I. N. Gritsenko, A. V. Lityshev, and S. I. Pantyushin p. 1461  abstract

Criteria for Evaluating the Combustion Modes of Mixtures Containing H2 and CO in NPP Containments: Part I. Flammability

T. A. Yudina, A. E. Kiselev, V. N. Semenov, A. I. Gavrikov, A. V. Kosheev, A. V. Avdeenkov, E. V. Bezgodov, V. A. Simonenko, O. V. Shultz, I. A. Melnikov, and Yu. A. Zvonarev p. 1468  abstract

Criteria for Evaluating the Combustion Modes of Mixtures Containing H2 and CO in NPP Containments: Part II. Flame Acceleration and Detonation

T. A. Yudina, A. E. Kiselev, V. N. Semenov, A. I. Gavrikov, A. V. Kosheev, A. V. Avdeenkov, E. V. Bezgodov, V. A. Simonenko, O. V. Shultz, I. A. Melnikov, and Yu. A. Zvonarev p. 1483  abstract

Estimation of the Xenon Diffusion Coefficient in Uranium Dioxide Microfuel Kernels

M. A. Agulnik, N. S. Bezruk, A. V. Grol, and A. S. Ivanov p. 1503  abstract

Silicon As an Effective Carbide Former in (U, Pu) N-Fuel Containing Carbon and Oxygen Impurities

A. S. Ivanov and V. A. Rusinkevich p. 1509  abstract

Some Features of Nitride Fuel Interaction with Fuel Rod Claddings of Austenitic and Ferritic-Martensitic Steel

V. A. Rusinkevich and A. S. Ivanov p. 1518  abstract

Evaluation of the Influence of Structural Parameters on the Long-Term Strength Characteristics of High-Nickel Steel for the Vessels of Promising VVER-Type Reactors

E. A. Kuleshova, I. V. Fedotov, A. A. Potekhin, D. A. Maltsev, S. P. Kuznetsov, and I. A. Ivanov p. 1526  abstract

Features of Macro- and Microstructure of the Weld Metal of VVER Reactor Pressure Made Using Ceramic Flux in the Initial and Irradiated States

E. A. Kuleshova, E. D. Malinovskiy, D. A. Maltsev, I. V. Fedotov, A. A. Potekhin, and V. N. Skorobogatykh p. 1538  abstract

Efficient Numerical and Analytical Method for Calculating Stress Intensity Factors at Boundary Crack Tips for Probabilistic Analysis of Equipment and Pipeline Failure

V. V. Matkovsky and A. V. Andreev p. 1554  abstract