袗胁褌芯褉写褘遥 卸邪褉懈褟谢邪薪褘屑写邪褉褘
Kulsartov, T.
袘邪褉谢褘覜 卸邪褉懈褟谢邪薪褘屑写邪褉
33
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
2
2026 (4)
- 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
- Development of irradiation capsule design and plan for neutron irradiation of chromium beryllide samples in the WWR-K reactor
- Effect of neutron irradiation on high-temperature corrosion of titanium beryllide Be12Ti in a steam-argon environment
2025 (8)
- Comparative analysis of high-temperature corrosion processes of beryllides of different compositions
- Gas release kinetics from neutron irradiated Li2TiO3 samples
- 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
- Simulation of tritium release processes from lithium ceramics under reactor irradiation conditions with varying reactor power
- Kinetic analysis of tritium release from irradiated biphasic lithium ceramics Li4SiO4-Li2TiO3 with different phase ratios
- 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)
2024 (4)
- Investigation of the interaction of deuterium with Sn73Li27 tin-lithium alloy
- Studies of irradiated two-phase lithium ceramics Li4SiO4/Li2TiO3 by thermal desorption spectroscopy
- 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
2023 (7)
- Study of Gas Swelling Processes under Irradiation with Protons and He2+ Ions in Li4SiO4鈥揕i2TiO3 Ceramics
- Radiation Resistance of Fiber Bragg Gratings under Intense Reactor Irradiation
- 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
- Investigation of transient processes of tritium release from biphasic lithium ceramics Li4SiO4-Li2TiO3 at negative neutron flux pulse
- Radiation-induced attenuation in single-mode pure-silica-core optical fibers two years after high-fluence reactor irradiation
2022 (4)
- 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
- Analysis of the reactor experiments results on the study of gas evolution from two-phase Li2TiO3-Li4SiO4 lithium ceramics
2021 (6)
- Modeling of hydrogen isotopes release from lithium ceramics Li2TiO3 during in-situ experiments using vacuum extraction method
- Radiation resistance of single-mode optical fibres with view to in-reactor applications
- Experiments on tritium generation and yield from lithium ceramics during neutron irradiation
- The study of deuterium permeability of film-forming inhibitors with the addition of fullerenes
- Determination of the activation energy of tritium diffusion in ceramic breeders by reactor power variation
- Features of the in-situ experiments on studying of tritium release from lithium ceramic Li2TiO3 using vacuum extraction method