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1. Research in the Field of Controlled Thermonuclear Fusion in the Republic of Kazakhstan
2. RESEARCH IN THE FIELD OF CONTROLLED THERMONUCLEAR FUSION SYNTHESIS IN THE REPUBLIC OF Kazakhstan
3. Experimental Simulation of Decay Heat of Corium at the Lava-B Test-Bench
4. Heat-Resistant Composite Coating with A Fluidized Bed of the Under-Reactor Melt Trap of A Light-Water Nuclear Reactor
5. Tests of fuel elements with uranium-plutonium nitride fuel in an IGR pulsed reactor
6. Diagnostics of Long-Term Erosion and Deposition of the Material of the First Wall in the KTM Tokamak: Testing and First Results
7. High-temperature test of tin-lithium CPS under deuterium plasma irradiation conditions
8. Investigation of the interaction of liquid tin-lithium alloy with austenitic stainless steel at high temperatures
9. Development of the technological process for the IGR reactors highly-enriched irradiated uranium-graphite fuel immobilization
10. ANALYSIS OF METHODS FOR SIMULATING THE DECAY HEAT IN CORIUM WHEN MODELING A SEVERE ACCIDENTS AT NUCLEAR POWER PLANT
11. Electrocatalyst For Solid Oxide Fuel Cells Operating at Intermediate Temperatures
12. La₂CuO₄ Electrode Material For Low Temperature Solid Oxide Fuel Cells
13. The main structural-phase states of interaction between model corium of a nuclear reactor and a sacrificial material based on Al₂O₃ and a lead layer
14. THE METHOD OF CORIUM COOLING IN A CORE CATCHER OF A LIGHT-WATER NUCLEAR REACTOR
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