袩褍斜谢懈泻邪褑懈懈 邪胁褌芯褉邪
Chikhray, Y.
袙褋械谐芯 锌褍斜谢懈泻邪褑懈泄
27
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)
- 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
- Development of irradiation capsule design and plan for neutron irradiation of chromium beryllide samples in the WWR-K reactor
2025 (7)
- Simulation of tritium release processes from lithium ceramics under reactor irradiation conditions with varying reactor power
- 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
- 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 (1)
2023 (3)
- 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
- Investigation of transient processes of tritium release from biphasic lithium ceramics Li4SiO4-Li2TiO3 at negative neutron flux pulse
2022 (5)
- Studies of two-phase lithium ceramics Li4SiO4-Li2TiO3 under conditions of neutron irradiation
- Irradiation capsule design for neutron coloration of topaz in a WWR-K reactor
- 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)
2021 (8)
- Experiments on tritium generation and yield from lithium ceramics during neutron irradiation
- Radiation resistance of single-mode optical fibres with view to in-reactor applications
- Application of High-Energy Tritium Ions and Alpha Particles Formed in 6Li(n,伪)T Nuclear Reaction to Excite the Luminescence of Inert Gas Mixtures
- Determination of the activation energy of tritium diffusion in ceramic breeders by reactor power variation
- Feasibility study on tritium recoil barrier for neutron reflectors of research and test reactors
- 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
- The study of deuterium permeability of film-forming inhibitors with the addition of fullerenes