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1. Experimental Facility to Study the Threshold Characteristics of Laser Action at the p-s-Transition of Noble Gas Atom upon Excitation by 6Li(n,α)3H Nuclear Reaction Products
2. High-Energy Tritium Ion and α-Particle Release from the Near-Surface Layer of Lithium During Neutron Irradiation in the Nuclear Reactor Core
3. Comparative analysis of high-temperature corrosion processes of beryllides of different compositions
4. High-temperature corrosion testing of titanium beryllides in the presence of water vapor and oxygen
5. High-temperature interaction of water vapor with lithium ceramics Li2TiO3
6. Study of the mechanisms of change in hydride phases in zirconium beryllide during its linear heating
7. Investigation of tritium and helium generation and release from tin-lithium alloy under neutron irradiation
8. Technique of Reactor Experiments of Tin-Lithium Alloy Interaction with Hydrogen Isotopes Under Neutron Irradiation Conditions
9. Investigation of the IGR research reactors uranium-graphite fuels high-temperature corrosion by a combination of thermal analysis and mass-spectrometry methods
10. Study of liquid tin-lithium alloy interaction with structural materials of fusion reactor at high temperatures
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