Kulsartov T 1

1. The study of deuterium permeability of film-forming inhibitors with the addition of fullerenes
2. Analysis of reactor experiments to study the transfer processes of generated tritium in lithium cps (capillary-porous system)
3. Gas release kinetics from neutron irradiated Li₂TiO₃ samples
4. Kinetic analysis of tritium release from irradiated biphasic lithium ceramics Li₄SiO₄-Li₂TiO₃ with different phase ratios
5. Experiments on tritium generation and yield from lithium ceramics during neutron irradiation
6. Calculation of Temperature Fields in a Lithium Ceramic Pebble Bed during Reactor Irradiation in a Vacuum
7. Studies of irradiated two-phase lithium ceramics Li₄SiO₄/Li₂TiO₃ by thermal desorption spectroscopy
8. Study of hydrogen sorption and desorption processes of zirconium beryllide ZrBe₂
9. Analysis of the reactor experiments results on the study of gas evolution from two-phase Li₂TiO₃-Li₄SiO₄ lithium ceramics
10. Study of Gas Swelling Processes under Irradiation with Protons and He²⁺ Ions in Li₄SiO₄–Li₂TiO₃ Ceramics
11. Comparative analysis of gas release from biphasic lithium ceramics pebble beds of various pebbles sizes and content under neutron irradiation conditions
12. Comparative analysis of high-temperature corrosion processes of beryllides of different compositions
13. Corrigendum to “Comparative analysis of gas release from biphasic lithium ceramics pebble beds of various pebbles sizes and content under neutron irradiation conditions” [Nucl. Mater. Energy 38 (2024) 101583] (Nuclear Materials and Energy (2024) 38, (S235217912400005X), (10.1016/j.nme.2024.101583))
14. Determination of the activation energy of tritium diffusion in ceramic breeders by reactor power variation
15. Estimation of tritium transfer parameters in biphasic lithium ceramic based on the results of reactor irradiation experiments
16. Features of Helium and Tritium Release from Li₂TiO₃ Ceramic Pebbles under Neutron Irradiation
17. Features of the in-situ experiments on studying of tritium release from lithium ceramic Li₂TiO₃ using vacuum extraction method
18. High-temperature corrosion testing of titanium beryllides in the presence of water vapor and oxygen
19. High-temperature interaction of water vapor with lithium ceramics Li₂TiO₃
20. Influence of various gases and water vapors on the processes of tritium release from two-phase lithium ceramics
21. Investigation of hydrogen and deuterium impact on the release of tritium from two-phase lithium ceramics under reactor irradiation
22. Investigation of the interaction of deuterium with Sn₇₃Li₂₇ tin-lithium alloy
23. Investigation of transient processes of tritium release from biphasic lithium ceramics Li₄SiO₄-Li₂TiO₃ at negative neutron flux pulse
24. Modeling of hydrogen isotopes release from lithium ceramics Li₂TiO₃ during in-situ experiments using vacuum extraction method
25. Reactor experiments on irradiation of two-phase lithium ceramics Li₂TiO₃/Li₄SiO₄ of various ratios
26. Simulation of tritium release processes from lithium ceramics under reactor irradiation conditions with varying reactor power
27. Studies of two-phase lithium ceramics Li₄SiO₄-Li₂TiO₃ under conditions of neutron irradiation
28. Study of the mechanisms of change in hydride phases in zirconium beryllide during its linear heating
29. Thermal desorption of tritium and helium from lithium ceramics Li₂TiO₃+5mol% TiO₂ after neutron irradiation
30. Investigation of the IGR research reactors uranium-graphite fuels high-temperature corrosion by a combination of thermal analysis and mass-spectrometry methods
31. Effect of low-temperature neutron irradiation on the properties of titanium beryllide
32. Effect of neutron irradiation on high-temperature corrosion of titanium beryllide Be₁₂Ti in a steam-argon environment
33. Irradiation experiments of titanium beryllide samples in the WWR-K reactor
34. Kinetics of gas release from titanium beryllide irradiated to different neutron fluences
35. Rig design development for in situ tritium release studies of EU reference ceramic breeders (ACB-TREND)
36. Phase Evolution and Synthesis of Be₁₂ Nb Intermetallic Compound in the 800–1300 °C Temperature Range
37. Determination of Tritium Transfer Parameters in Lithium Ceramics Li₂TiO₃ During Reactor Irradiation Based on a Complex Model
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