Mukhamedov N 1

1. Computational approaches for determining the nuclear heating value of structural materials during the irradiation at the IGR reactor
2. Decommissioning of the BN-350 Fast Neutron Reactor: History Review and Current Status
3. Properties and characteristics of corium prototype of a fast power reactor
4. The BN-350 Reactor Decommissioning: Quantitative Analysis and Prospects for Solid Radioactive Waste Management
5. Microstructural stability of a two-phase (O + B2) alloy of the Ti–25Al–25Nb system (at.%) during thermal cycling in a hydrogen atmosphere
6. Study of structural, surface energies, and tribomechanical properties of thermoplastics irradiated by electron beam
7. Establishing a relation between the energy parameters of the research impulse graphite reactor and the tested fuel assembly with a block structure
8. Testing of a heterogeneous fuel rod in the research Impulse graphite reactor
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