Kenzhin Y 1

1. Experiments on tritium generation and yield from lithium ceramics during neutron irradiation
2. Study of hydrogen sorption and desorption processes of zirconium beryllide ZrBe₂
3. Analysis of the reactor experiments results on the study of gas evolution from two-phase Li₂TiO₃-Li₄SiO₄ lithium ceramics
4. Comparative analysis of high-temperature corrosion processes of beryllides of different compositions
5. Determination of the activation energy of tritium diffusion in ceramic breeders by reactor power variation
6. High-temperature corrosion testing of titanium beryllides in the presence of water vapor and oxygen
7. Investigation of hydrogen and deuterium impact on the release of tritium from two-phase lithium ceramics under reactor irradiation
8. Modeling of hydrogen isotopes release from lithium ceramics Li₂TiO₃ during in-situ experiments using vacuum extraction method
9. Simulation of tritium release processes from lithium ceramics under reactor irradiation conditions with varying reactor power
10. Studies of two-phase lithium ceramics Li₄SiO₄-Li₂TiO₃ under conditions of neutron irradiation
11. Study of the mechanisms of change in hydride phases in zirconium beryllide during its linear heating
12. Analysis of lutetium-177 production at the WWR-K research reactor
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