Ponkratov Y 1

1. Analysis of reactor experiments to study the transfer processes of generated tritium in lithium cps (capillary-porous system)
2. Study of hydrogen sorption and desorption processes of zirconium beryllide ZrBe₂
3. Comparative analysis of high-temperature corrosion processes of beryllides of different compositions
4. Features of the in-situ experiments on studying of tritium release from lithium ceramic Li₂TiO₃ using vacuum extraction method
5. High-temperature corrosion testing of titanium beryllides in the presence of water vapor and oxygen
6. Investigation of hydrogen and deuterium impact on the release of tritium from two-phase lithium ceramics under reactor irradiation
7. Investigation of the interaction of deuterium with Sn₇₃Li₂₇ tin-lithium alloy
8. Studies of two-phase lithium ceramics Li₄SiO₄-Li₂TiO₃ under conditions of neutron irradiation
9. Study of the mechanisms of change in hydride phases in zirconium beryllide during its linear heating
10. Thermal desorption of tritium and helium from lithium ceramics Li₂TiO₃+5mol% TiO₂ after neutron irradiation
11. Application of High-Energy Tritium Ions and Alpha Particles Formed in ⁶Li(n,α)T Nuclear Reaction to Excite the Luminescence of Inert Gas Mixtures
12. Investigation of tritium and helium generation and release from tin-lithium alloy under neutron irradiation
13. Technique of Reactor Experiments of Tin-Lithium Alloy Interaction with Hydrogen Isotopes Under Neutron Irradiation Conditions
14. Investigation of the IGR research reactors uranium-graphite fuels high-temperature corrosion by a combination of thermal analysis and mass-spectrometry methods
15. Study of liquid tin-lithium alloy interaction with structural materials of fusion reactor at high temperatures
16. Phase Evolution and Synthesis of Be₁₂ Nb Intermetallic Compound in the 800–1300 °C Temperature Range
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