Vol. 87, No. 8, 2024
Development of the Physical and Technical Foundations of the Technology of High-Temperature Gas-Cooled Reactor Systems
p. 993 abstract
The Fusion Neutron Source as Part of a Nuclear Energy System
p. 1008 abstract
Artificial Intelligence in the Field of Atomic Energy Usage—Existing Possibilities and Perspectives
p. 1020 abstract
Machine Learning Method for Validation of the Computational Model of Nonstationary Xenon Processes in the VVER Reactor Based on the Algorithm of Separation of Variables
p. 1030 abstract
Advances in the Physical Start-Up Test Program for VVER-1200 Power Units
p. 1039 abstract
Results of Numerical Simulation of Measurements of Scram Worth Performed during the Start-Up Phase of the Second and Third Fuel Loads of the Novovoronezh NPP Unit 6
p. 1047 abstract
Study of the Properties of High-Sensitivity Self-Powered Neutron Detector
p. 1053 abstract
Experimental Study of the Gamma Component in the Rhodium SPD Signal
p. 1060 abstract
Self-Powered Neutron Detector with Hafnium Metal Emitter in VVER Reactors
p. 1064 abstract
Statistical Component of Calibration Error of VVER In-Core Thermal Sensors
p. 1067 abstract
Determination of the Characteristics of Neutron Field of the IGRIK-2 Reactor Using the Neutron Activation Method
p. 1073 abstract
Method of Homogenization of Group Neutronic Constants Taking into Account Heterogeneous and Kinetic Effects
p. 1078 abstract
Procedure for Taking into Account the Influence of the Neutron Field on Reactivity Effects in Engineering Calculations
p. 1083 abstract
PRIM-AES Software Package for Simulation of Transient Modes at Power Units with VVER Reactors
p. 1089 abstract
Using (Np, Am) Fractions of Minor Actinides for 238Pu Production in a VVER-Type Reactor
p. 1101 abstract
Uncertainty in the Prediction of the Neutronic Characteristics of the RBMK Reactor Related to the Choice of the Graphite Stack Repair Scheme
p. 1106 abstract
Code for Calculating Temperature Fields in RBMK KLADKA-2
p. 1114 abstract
Numerical Simulation of Fluid Flow and Heat Transfer at Supercritical Pressures of Water Coolant for a Wire-Wrapped Rod Bundle
p. 1123 abstract
Trends of Structure Degradation of VVER-1000 Reactor Pressure Vessel Steels Determining Their Performance at Lifetimes of over 60 Years
p. 1138 abstract
Preliminary Calculated and Experimental Assessments of the Possibility of Using High-Nickel Steels for Pressure Vessels of Next Generation VVERs
p. 1151 abstract
Application of Miniature Specimens for Off-Center Tension Aimed at Determination of Fracture Toughness of Steels of VVER-1000 Reactor Vessel in the Ductile–Brittle Transition Zone
p. 1159 abstract
Container Materials for Molten Salt Nuclear Reactors: Problems and Research
p. 1166 abstract
Experimental Study of Corrosion Resistance of Nickel-Molybdenum Alloys in the Melt of Lithium and Beryllium Fluoride Salts
p. 1176 abstract
Radiation-Chemical Fixation of Nitrogen in an Aqueous Solution of H2 and N2 under Accelerated Proton Irradiation. Mathematical Model and Its Verification
p. 1187 abstract