Vol. 89, No. 1, 2026
Analysis of Density Profile Peaking during On-Axis ECR-Heating in the T-10 Tokamak
p. S1 abstract
High Power CO2 Laser System “FOKUS” for Laser Produced Plasma Applications
p. S16 abstract
Study of the Plasma-Forming Gas Injection into the Interelectrode Gap of the MK-200 Plasma Gun
p. S29 abstract
Fusion Safety Regulation: Analysis of Approaches Suggested Worldwide and Their Applicability in Russia
p. S40 abstract
Influence of Pulsed Laser Radiation on the Morphology and Surface Properties of Tungsten Implanted with Helium Ions
p. S48 abstract
Testing of AlN–TiB2 Ceramics by Pulsed-Periodic Thermal Load Possible in Fusion Devices
p. S56 abstract
Development of Current Leads of a Facility for Testing Coils of Thermonuclear Devices
p. S69 abstract
Development of Superconducting Subcables for High-Current Cables
p. S76 abstract
Development of Interfaces for Coupled Calculations for the Analysis of Hydrogen Safety of Tokamak Thermonuclear Facilities
p. S83 abstract
Ensuring the Operation of the Atomic Beam Injector of a Tokamak with Reactor Technologies
p. S96 abstract
Analysis of the Spatial Spectrum of Plasma Perturbations in a Tokamak Based on the Cross-Coherence of MHD Diagnostic Signals
p. S102 abstract
Assessment of Capabilities for Ensuring Radiation Safety of Personnel at the T-15MD Facility during Operation with Deuterium Fuel
p. S110 abstract
Studies of Ultraviolet Radiation from Hydrogen-Xenon Plasma at the Plasma Focus Facility
p. S121 abstract
Implementation of Automated Calculations of Sputtering and Scattering Characteristics during Ion Bombardment of a Solid Target
p. S128 abstract
Simulation of Magnetic Fields in the MEPhIST-0 Tokamak at the Beginning of Discharge
p. S136 abstract
First Results of Work with a Lithium Injector with External Lithium Supply in Plasma Discharges of the T-11M Tokamak
p. S147 abstract
Evolution of Concepts of the Resistance of the First Wall to Pulsed Thermal Loads in ITER
p. S156 abstract
Experience in Licensing the ITER Fusion Project
p. S168 abstract
Monitoring the Impurity Influx into Plasma Using HA&VS Diagnostic in the New ITER Baseline with a Tungsten Wall
p. S177 abstract