Sapatayev Y 1
1. High-Temperature Corrosion Behavior of 12Cr18Ni10Ti Grade Austenitic Stainless Steel Under Chlorination Conditions
2. High-temperature corrosion testing of titanium beryllides in the presence of water vapor and oxygen
3. Properties and characteristics of corium prototype of a fast power reactor
4. An experimental study using CeO2, ZrO2, and SUS316L powders as simulated nuclear fuel materials to examine the process of fuel debris formation
5. Investigation of the IGR research reactors uranium-graphite fuels high-temperature corrosion by a combination of thermal analysis and mass-spectrometry methods
6. Impact of High-Power Heat Load and W Surface Carbidization on Its Structural-Phase Composition and Properties
7. The Neutron Absorption Capacity of a Composite Material Based on Ultrahigh Molecular Weight Polyethylene Under Reactor Radiation Conditions
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