袗胁褌芯褉写褘遥 卸邪褉懈褟谢邪薪褘屑写邪褉褘
Askerbekov, S.
袘邪褉谢褘覜 卸邪褉懈褟谢邪薪褘屑写邪褉
32
袘械谢褋械薪写褨谢褨泻 卸褘谢写邪褉褘
5
袞邪褉懈褟谢邪薪褘屑 褌爷褉谢械褉褨
2
2026 (3)
- Study of isotopic effects of high-temperature corrosion of titanium beryllide Be12Ti in water vapor with different isotopic composition
- Modeling experimental dependencies of deuterium penetration through SS316IG stainless steel under reactor irradiation conditions
- Effect of neutron irradiation on high-temperature corrosion of titanium beryllide Be12Ti in a steam-argon environment
2025 (13)
- The Influence of Accumulated Radiolysis Products on the Mechanisms of High-Temperature Degradation of Two-Component Lithium-Containing Ceramics
- Gas release kinetics from neutron irradiated Li2TiO3 samples
- Low-temperature sintering of zirconia-based ceramic composites for capacitor applications
- Estimation of tritium transfer parameters in biphasic lithium ceramic based on the results of reactor irradiation experiments
- STUDY OF THE EFFECT OF THE COMPONENT RATIO VARIATION IN TWO-PHASE CERAMICS ON THE RESISTANCE TO HIGH-DOSE PROTON IRRADIATION SIMULATING THE EFFECTS OF HYDROGEN SWELLING
- Determination of Tritium Transfer Parameters in Lithium Ceramics Li2TiO3 During Reactor Irradiation Based on a Complex Model
- Simulation of tritium release processes from lithium ceramics under reactor irradiation conditions with varying reactor power
- Comparative analysis of high-temperature corrosion processes of beryllides of different compositions
- Kinetic analysis of tritium release from irradiated biphasic lithium ceramics Li4SiO4-Li2TiO3 with different phase ratios
- Effects of the Zirconia-Alumina Composite Ceramics with Varying Compositions on Resistance to Helium Swelling
- Method of measurement of residual tritium in irradiated lithium ceramics
- Rig design development for in situ tritium release studies of EU reference ceramic breeders (ACB-TREND)
- The effect of mechanical milling and two-step sintering technique on the microstructure, microhardness, strength, and dielectric properties of Sm2Zr2O7 ceramics
2024 (5)
- Study of the mechanisms of change in hydride phases in zirconium beryllide during its linear heating
- High-temperature corrosion testing of titanium beryllides in the presence of water vapor and oxygen
- The connection between the accumulation of structural defects caused by proton irradiation and the destruction of the near-surface layer of Li4SiO4 鈥� Li2TiO3 ceramics
- Investigation of the interaction of deuterium with Sn73Li27 tin-lithium alloy
- Studies of irradiated two-phase lithium ceramics Li4SiO4/Li2TiO3 by thermal desorption spectroscopy
2023 (6)
- Irradiation experiments of titanium beryllide samples in the WWR-K reactor
- Radiation-induced attenuation in single-mode pure-silica-core optical fibers two years after high-fluence reactor irradiation
- Influence of the Change of Phase Composition of (1 鈭� x)ZrO2鈥搙Al2O3 Ceramics on the Resistance to Hydrogen Embrittlement
- Investigation of transient processes of tritium release from biphasic lithium ceramics Li4SiO4-Li2TiO3 at negative neutron flux pulse
- Study of Gas Swelling Processes under Irradiation with Protons and He2+ Ions in Li4SiO4鈥揕i2TiO3 Ceramics
- Features of Helium and Tritium Release from Li2TiO3 Ceramic Pebbles under Neutron Irradiation
2022 (5)
- Analysis of reactor experiments to study the transfer processes of generated tritium in lithium cps (capillary-porous system)
- Study on the effect of long-term high temperature irradiation on TRISO fuel
- Study of Morphological, Structural, and Strength Properties of Model Prototypes of New Generation TRISO Fuels
- Studies of two-phase lithium ceramics Li4SiO4-Li2TiO3 under conditions of neutron irradiation
- Investigation of hydrogen and deuterium impact on the release of tritium from two-phase lithium ceramics under reactor irradiation