袩褍斜谢懈泻邪褑懈懈 邪胁褌芯褉邪
Shaimerdenov, A.
袙褋械谐芯 锌褍斜谢懈泻邪褑懈泄
32
袥械褌 邪泻褌懈胁薪芯褋褌懈
6
孝懈锌芯胁 锌褍斜谢懈泻邪褑懈泄
2
2026 (3)
- 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
- Modeling experimental dependencies of deuterium penetration through SS316IG stainless steel under reactor irradiation conditions
2025 (8)
- Gas release kinetics from neutron irradiated Li2TiO3 samples
- Method of measurement of residual tritium in irradiated lithium ceramics
- Kinetic analysis of tritium release from irradiated biphasic lithium ceramics Li4SiO4-Li2TiO3 with different phase ratios
- 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
- Enhancing photogenerated charge separation in perovskite semiconductors via dual cocatalyst engineering
- Rig design development for in situ tritium release studies of EU reference ceramic breeders (ACB-TREND)
2024 (2)
2023 (6)
- Investigation of transient processes of tritium release from biphasic lithium ceramics Li4SiO4-Li2TiO3 at negative neutron flux pulse
- 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
- Radiation Resistance of Fiber Bragg Gratings under Intense Reactor Irradiation
2022 (6)
- Irradiation capsule design for neutron coloration of topaz in a WWR-K reactor
- TITAN neutron imaging facility performance
- Investigation of hydrogen and deuterium impact on the release of tritium from two-phase lithium ceramics under reactor irradiation
- Analysis of the reactor experiments results on the study of gas evolution from two-phase Li2TiO3-Li4SiO4 lithium ceramics
- Studies of two-phase lithium ceramics Li4SiO4-Li2TiO3 under conditions of neutron irradiation
- Study on the effect of long-term high temperature irradiation on TRISO fuel
2021 (7)
- Experiments on tritium generation and yield from lithium ceramics during neutron irradiation
- Analysis of lutetium-177 production at the WWR-K research reactor
- Radiation resistance of single-mode optical fibres with view to in-reactor applications
- Features of the in-situ experiments on studying of tritium release from lithium ceramic Li2TiO3 using vacuum extraction method
- Modeling of hydrogen isotopes release from lithium ceramics Li2TiO3 during in-situ experiments using vacuum extraction method
- Time History of Performance Parameters of WWR-K Reactor during Gradual Replacement of the Water Reflector by a Beryllium One
- Non-destructive analysis of materials by neutron imaging at the TITAN facility