A5057724614- Nuclear Materials and Properties
- Fusion materials and technologies
- Nuclear reactor physics and engineering
- Graphite, nuclear technology, radiation studies
- Advanced materials and composites
- Metal and Thin Film Mechanics
- Powder Metallurgy Techniques and Materials
- Radioactive element chemistry and processing
- Mineral Processing and Grinding
- Magnesium Alloys: Properties and Applications
- Radiation Shielding Materials Analysis
- Nuclear Physics and Applications
- Mechanical Failure Analysis and Simulation
- Aluminum Alloys Composites Properties
- Surface Treatment and Residual Stress
- Metallurgy and Material Forming
- Tribology and Wear Analysis
- Surface Treatment and Coatings
- Microstructure and Mechanical Properties of Steels
- Material Properties and Applications
- Nuclear and radioactivity studies
- Radiation Detection and Scintillator Technologies
- Intermetallics and Advanced Alloy Properties
- Vacuum and Plasma Arcs
- Superconducting Materials and Applications
National Nuclear Center of the Republic of Kazakhstan
2019-2024
Institute of Atomic Energy
2019-2022
D. Serikbayev East Kazakhstan State Technical University
2013
Abstract This work is devoted to the investigation of tungsten surface after exposure Ar + , and He . Plasma irradiation experiments were conducted in a plasma-beam installation. The analysis modification was carried out by scanning electron microscopy contact profilometry. As result studies conducted, it found that on argon plasma shows «relief etching». It assumed formation relief occurs mainly due dispersion high ion energy cascade mechanism. After He, areas with wavy structure observed...
The luminescence of Kr-Xe, Ar-Kr, and Ar-Xe mixtures was studied in the spectral range 300–970 nm when excited by 6 Li ( n, α ) 3 H nuclear reaction products core a reactor. Lithium deposited on walls experimental cell form capillary-porous structure, which made it possible to measure up temperature 730 K. dependence radiation intensity noble gas atoms, alkali metals, heteronuclear ionic molecules studied. Also, as case single-component gases, appearance lithium lines impurities sodium...
This paper presents the results of a study on impact high-power heat load and tungsten (W) surface carbidization its structural-phase composition physical-mechanical properties. In this regard, W was carried out by means beam-plasma discharge in simulation machine with plasma-beam installation. Certain data were obtained regarding temperature control points studied samples distribution throughout monoblock element, made as rectangle an orifice for cooling path, placed fusion reactor...
This work presents the results of a study on influence fillers neutron absorption capacity materials made from ultra-high molecular weight polyethylene (UHMWPE). Composite based UHMWPE were obtained using gas-flame technology with addition powdered (H3BO3, WC, and PbO). A radiation cassette has been developed constructed for conducting studies material, allowing placement sample activation indicators. Samples irradiated at different doses unique research reactor IVG-1M, located National...
There are results of long-term thermal aging samples irradiated and nonirradiated FA jacket fuel element cladding at a temperature range from 300 to 550°C in argon, 600°C air. Materials have been studied before after tests. The forecast estimation expected corrosion damage barrier material the radionuclide release spent assemblies BN-350 reactor into environment during dry storage for 50 years was carried out.
In this work, to assess the radiation damage of beryllium under low-temperature neutron irradiation, samples from grade TShG-200 with an oxide phase concentration about 1 wt % were studied, which kept in IVG.1M research reactor for a long time and irradiated fluences 0.8–4·10 20 neut./cm 2 . Also, unirradiated original witness same brand tested compare results.The aim was establish level degradation during their tests reactor. Mechanical three-point bending tension performed determine...
In this work the microstructure and microhardness distribution of modified layers 40Cr (AISI 5140) alloy steel after nitriding by electrolytic plasma have been under research. It is shown that as a result it becomes possible to increase surface steel.
This paper presents the results of research influence nitriding in electrolytic plasma on tribological properties low-alloy 40Cr steel. It is shown that process can significantly increase wear resistance samples Found after component adhesive mechanism changed to abrasion.
The results of corrosion damage to the surface fragments SFA cover after neutron irradiation in a BN-350 reactor and subsequent “wet” storage are presented. relative value deflection as result radiation swelling creep fuel assemblies was determined.
The paper presents the results of mechanical tests to determine changes in strength characteristics material zirconium alloy E125 after local thermal exposure. Dependences on hardness are determined. maximum and minimum values zones reflow heat exposure have been An assessment change geometric parameters heat- affected spot from modes arc action conditions subsequent cooling is carried out.
In this paper, experiments were conducted on the thermal effect of an electron beam beryllium TGP-56 grade in vacuum, at values surface temperature ~ 360 °C, ~800 °C and 1200 with number pulses 10 100 same pulse duration – 500 s. A complex material research such as microanalysis, x-ray diffraction analysis, determination microhardness was conducted. The experimental data changes mechanical properties melting conditions boundary between gaps plates ITER first wall a result heat loads...
The paper presents the results of development and manufacture, as well assembly installation a test device for testing miniature samples by SPT method. mechanical tests tensile methods 35X steel material after heat treatment (quenching + tempering) at different tempering temperatures. evaluation changes in strength characteristics grade 35X, depending on mode. correlation equations between t/10 method yield each sample obtained during were determined obtained.