袗胁褌芯褉写褘遥 卸邪褉懈褟谢邪薪褘屑写邪褉褘
Zaurbekova, Z.
袘邪褉谢褘覜 卸邪褉懈褟谢邪薪褘屑写邪褉
26
袘械谢褋械薪写褨谢褨泻 卸褘谢写邪褉褘
6
袞邪褉懈褟谢邪薪褘屑 褌爷褉谢械褉褨
1
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 (6)
- Simulation of tritium release processes from lithium ceramics under reactor irradiation conditions with varying reactor power
- 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
- Determination of Tritium Transfer Parameters in Lithium Ceramics Li2TiO3 During Reactor Irradiation Based on a Complex Model
- Comparative analysis of high-temperature corrosion processes of beryllides of different compositions
- The effect of mechanical milling and two-step sintering technique on the microstructure, microhardness, strength, and dielectric properties of Sm2Zr2O7 ceramics
2024 (3)
2023 (6)
- 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
- Thermal desorption of tritium and helium from lithium ceramics Li2TiO3+5mol% TiO2 after neutron irradiation
- 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
2022 (5)
- Analysis of the reactor experiments results on the study of gas evolution from two-phase Li2TiO3-Li4SiO4 lithium ceramics
- Investigation of hydrogen and deuterium impact on the release of tritium from two-phase lithium ceramics under reactor irradiation
- Analysis of reactor experiments to study the transfer processes of generated tritium in lithium cps (capillary-porous system)
- Studies of two-phase lithium ceramics Li4SiO4-Li2TiO3 under conditions of neutron irradiation
- Study of Morphological, Structural, and Strength Properties of Model Prototypes of New Generation TRISO Fuels
2021 (3)
- Features of the in-situ experiments on studying of tritium release from lithium ceramic Li2TiO3 using vacuum extraction method
- Determination of the activation energy of tritium diffusion in ceramic breeders by reactor power variation
- Experiments on tritium generation and yield from lithium ceramics during neutron irradiation