In this paper, the legal regulation in the field of accounting and control of nuclear materials in the Republic of Kazakhstan is considered. The laws and regulations of the Republic of Kazakhstan in the field of peaceful use of atomic energy are analyzed. A list of existing nuclear facilities and facilities for the use of atomic energy in the republic is given.

Particular attention is paid to the legislative and regulatory framework, due to the potential danger of using atomic energy, as well as the presence of materials and technologies dual-use which can be used not only for peaceful purposes. The application of international safeguards considered is in connection with the agreement between the Republic of Kazakhstan and IAEA on the basis of the Treaty on the Non-Proliferation of Nuclear Weapons, entered into force on August 11, 1995.

The activities of the committee of atomic and energy supervision and control of the Ministry of Energy of the Republic of Kazakhstan, which performs control and implementation functions in the field of atomic energy and electric power industry, are analyzed.

The methods of nuclear gamma-resonance spectroscopy (MS), X-ray diffraction (XRD) and X-ray fluorescence analysis (XRF) have been used to study the Kazakhstan’s coal from the deposits Ekibastuz, Shubarkol and Karazhyrinsky. It has been established that iron in the coals is contained in the divalent and trivalent states. The bivalent iron forms siderite mineral FeCO₃, the trivalent iron forms pyrite mineral FeS₂. During combustion of coal both pyrite and siderite decompose into Fe, sulfur oxide SO₂ and carbon dioxide CO₂ at the temperature of ~500 °C. The process of coal combustion occurs at high temperatures with formation of ash that contains the newly formed minerals – magnetite Fe₃O₄, hematite α-Fe₂O₃, mullite Al₆Si₂O₃, hercynite FeAl₂O₄ in the composition of the ferro- and cenospheres.

In this paper the ion-induced structural-phase transformations in austenitic stainless steels 12Cr18Ni10Ti, AISI 316 and AISI 304 have been studied by the Mössbauer spectroscopy of conversion electrons, X-ray diffraction and scanning microscopy. It has been established, that the electronic structure of the Mössbauer atoms in stainless steels AISI 304 and AISI 316 are different. Consequently, molybdenum does not affect the short-range order of ⁵⁷Fe in AISI 316 steel. Implantation of its own atoms (⁵⁷Fe) in AISI 316 steel leads, as in case with AISI 304 and 12Cr18Ni10Ti steel, to martensitic transformations. Among three steels AISI 316 was found to be the most stable to the ion-induced structural phase transformations.

The study of radiation erosion began in the 50–70 s of the last century. It was relatively quickly shown that the removal of atoms and molecules from the surface when irradiated with low-current beams of accelerated ions with energies of 10²–10⁴ eV occurs as a result of pairwise collisions of fast particles with atoms of matter, i.e. so-called collision spraying. Cosmic ray muons are also high-energy charged particles, and therefore there is a possibility that they, too, can destroy the structure of solids when hit. It is this property of muons that suggested that they can be used to predict and monitor earthquakes in seismically active zones. Muons falling into the earth's crust gives rise to EAS and streams of different particles when interacting with atoms of certain rocks can destroy their structure and, as a result, this destruction (cracks) is accompanied by acoustic effects.

At present, in cosmic rays at energies above 1015 eV, a certain number of phenomena are observed mainly in the trunk (center) region of a wide air shower (EAS) that do not fit into the traditional concepts of the nuclear cascade process in the atmosphere. If we consider that the trunk region with a radius of up to 10 meters at a distance of 20–30 km from the point of the first interaction of a particle that produced an EAS, belongs to the pseudo-fastness region that is inaccessible on accelerators, then the study of the central part of EAS is a good addition to accelerator experiments. It is also possible that unusual particles can be present in the cosmic-ray flux at energies above 1015 eV, which are the primary cause of the observed anomalous phenomena in experiments with cosmic radiation and which, due to their properties, are not observed in accelerator experiments. The complex installation “ADRON-55” is located at an altitude of 3340 meters above sea level and is part of the unified system of registration of particles of cosmic radiation at the Tian-Shan high-altitude scientific station. The “ADRON-55” facility is aimed at solving a number of astrophysical and nuclear physics problems: the study of interactions of high-energy hadrons in the central part of EAS trunks, the search for sources of high-energy cosmic rays.

Non-uniform distribution (both vertical and radial) of the neutron field in the reactor core of the research reactors is one of the most important task to solve in the process of neutron-transmutation doping of semiconductors. Since 2017, using the critical facility, the Institute of Nuclear Physics (Republic of Kazakhstan), in cooperation with с Chiyoda Technol Corporation (Japan), has been developing an irradiation device for the maximally reduce axial non-uniformity factor of the thermal neutron flux. The developed device allows to reduce the axial non-uniformity factor from 18% to 4%. The present work shows the methods to measure axial distribution of the neutron flux density, and the results of the experiments conducted on the critical facility. Cadmium was used for thermal neutron absorption. The irradiation device has a cadmium-screen formed of cadmium rings 0,5 mm wide and from 3 mm to 5 mm high.

Since 2019, works on the modernization of management information systems of the "EAGLE" test bench are carried out at the Institute of Atomic Energy. The tasks are formulated, which will be solved during modernization. Algorithms of data processing from primary converters and visualization methods and presentation of information on the screens of operators of consoles are developing. The result of this work will be the improvement of the control process, registration, display of experimental information on the "EAGLE" test bench.

The comparative study has been performed on the post-operation changes in the structural-phase state, magnetization, swelling and corrosion properties of the samples of structural reactor steel 12Cr18Ni10Ti, cut from the walls of the hexagonal ducts of the spent fuel assemblies from various elevations from the core center of the nuclear reactor BN-350. The studies of the aging processes in the highly irradiated corrosion-resistant austenitic steel showed that as the result of isochronous annealing in the region of 400÷450 °C we can observe the effect of magnetization increase, initiation of the processes of nucleation of defects of various morphology, the changes in their density and size, which determines the degree of swelling. The relationship has been established between radiation swelling with evolution of the defective structure, density, magnetization and corrosion resistance of austenitic steel.

In accordance with purpose of the program for ensuring scientific study efficiency, an experimental simulation bench with a plasma-beam installation was created based on IAE Branch RSE NNC RK at the KTM installation, in 2008, whose role is the testing of small samples from promising structural materials and the setting up of diagnostic equipment for thermonuclear reactors. The installation is oriented on universality and possibility of quick readjustment to solve various specialized tasks, and also has wide possibility and allows testing materials under the complex effect of plasma flow and powerful heat load on them.

The stationary linear plasma simulators was reviewed, which are used to study the interaction between plasma and surface with regard to fusion facilities and modeling of their edge plasma. The interaction between plasma and surface is an important issue in creation of protective materials for the International Thermonuclear Experimental Reactor (ITER). The first wall and divertor are the key plasma faced components. The basic functions of the divertor are a heat flux absorption released from the edge plasma and helium removal, which is a combustion product in the thermonuclear synthesis reaction. Relatively small facilities with limited capacities as well as large linear simulators with a capacity of several dozen of kW and various diagnostic tools have been considered separately. Since the modern linear installations have a temperature and density of the generated plasma close to SOL plasma (scrap-off layer), it is possible to research the processes which directly affect materials of the components. This is a modification of surface during plasma irradiation or with charged particle beams. This includes atomization of a surface and studying of erosion, penetration of foreign particles into the surface or coating, surface relief modification, blister generation.

Based on this article, high-voltage porcelain ceramics was prepared as local raw materials. According to state standard (GOST 7025-91), density, water absorption, and volume shrinkage were determined. A structural analysis was carried out using a scanning electron microscope, and an X-ray phase analysis was carried out on an Xpert PRO diffractometer. It was found, that in the initial state, ceramics consist of hexagonal (SiO₂) and in a small amount of monoclinic phase, above a temperature of 1150 °С it consists of hexagonal (SiO₂), an orthorhombic lattice, and also contains mullite (Al₂Si₂O₁₃).

In Kazakhstan, for a long time, work has been underway to justify the possibility to use atomic energy for industrial development of the country. This article provides an overview of the work done to develop the marketing section of the feasibility study for the construction of a nuclear power plant in the Republic of Kazakhstan, regarding the comparative analysis of the reactor technologies available on the market. Analysis of reactor designs for potential construction in the Republic of Kazakhstan was carried out according to a system of evaluation criteria developed by specialists of the RSE National Nuclear Center of the Republic of Kazakhstan. In the course of the assessment, the most promising reactor designs for possible construction in the Republic of Kazakhstan were proposed.

This paper is devoted to issues of creating the reactors that ensure high efficiency of natural raw use for fuel materials of reactors, possibility to enhance the pace of atomic energy development in the nearest future. Methods and stages for achieving these goals are shown including the example of work of the staff of NNC RK. Technical solutions used at the initial stage, are based on reduction of neutron losses in thermal reactors, use of ²³³U as fission material. The solution of the problem of nuclide activity reduction in ²³²U chain lead to possibility to increase fission proportions on fast neutrons in the fuel of thermal reactor. Created advanced type of fast thermal reactor ensures increasing of fission proportion on fast neutrons up to 30%, at small amount of fission materials typical for thermal reactor.

At the current stage of space exploration development, missions to the Moon and geostationary orbit are relevant. Enhancing of power supply level of such missions requires innovative technology development. Nuclear rocket engines and engines with use of solar energy are considered among such technologies. In a number of projects, such engines use intermediate heat energy accumulators, which complicates and increases the cost of construction. This embodiment uses a circuit that enables solar engine to operate with any orientation of the thrust direction towards the sun. The dependence of specific thrust of such engine on maximum heating temperature of working fluid (hydrogen) is shown. Such engines provide the ability to return to Earth at a speed of 8 km/s instead of 11 km/s, which increases flight safety and makes propulsion system reuse efficient.

Nuclear reactors based on fission of heavy nuclei were created a decade after the discovery of uranium fission by neutrons. Attempts to create reactors based on synthesis of light nuclei have been continuing for more than seven decades. The main direction of their implementation repeats natural technologies - implementation of reactions under the influence of high (stellar) temperatures. This direction has faced a lot of problems, and in the modern sense requires huge investments for its implementation. There are developments based on the use of accelerator technology. In this paper, there is an assessment of feasibility to create synthesis reactors using colliding ion beams of the D-D, D-T, D-3He reactions. The technical solutions applicable for their implementation are shown, advantages of such reactors over thermonuclear reactors, possibility of producing fuel for them and the problems that arise.

Transition of aviation to turbojet engines, which started actively in the forties of the 20th century, enabled significantly increasing flight speeds due to eliminating problems associated with peculiarities of propeller operation at high speeds. For many years, flights with turbojet engines at relatively low speeds (up to 500–700 km/h) were less cost-effective than on piston propeller airplanes. Development of aviation turbine technology has largely eliminated disadvantages of cost effectiveness. However, engines themselves have become more complicated, more expensive, but in recent years, the rate of increase in efficiency has been slow. The total fuel consumption increases due to the increase in traffic volume. Many problems in this area can be solved by using cost-efficient rotary-petal engines of internal combustion. Possible technical solutions for development of this area are shown.

The aim of this work was to study coatings deposited by the detonation method on the surface of stainless steel 12X18H10T. CCDS detonation complex, Xpert Pro X-ray analysis (U = 40 kV, I = 30 mA CuKα), Phenom ProX scanning electron microscope (SEM) and DuraScan-20 microstructure detection methods were used. The surface of the steel was covered by Al₂O₃ and ZrO₂ powders in 500 and 1100 μm thick. The thickness of the coating was measured and the elemental analysis was performed. Based on literary reviews and research, it was found that the covering of the metal with different coatings increases the physico-mechanical and tribological properties.

The paper provides the results of defect analysis in welded joints of pipelines of coolant cooling system of the IVG.1M reactor. It was defined that there are no defects in the cooling system making the most impact on the quality of joints (cracks, faulty fusion at the base of joints). The welding process of pipes is presented.

The results of corrosion damage to the surface of fragments of the SFA cover after neutron irradiation in a BN-350 reactor and subsequent “wet” storage are presented. The relative value of the deflection of the cover fragments as a result of radiation swelling and creep of fuel assemblies was determined.

Since 2015, X-ray diffraction studies at the Institute of Atomic Energy have been carried out on a modern Panalytical Empyrean X-ray diffractometer. Empyrean is a unique X-ray diffractometer with a vertically positioned high-resolution goniometer, which combines capabilities of a classic powder and research diffractometer. A number of works on budget programs, commercial and grant projects include x-ray structural studies. In each work, samples have typical features (geometric dimensions, thickness, radioactivity of the material, etc.), which should be taken into account when shooting diffraction patterns. It is important to ensure precision of diffraction patterns for several samples, simplicity of the sample preparation method, and acceptability to work from the point of view of radiation safety. To ensure the quality components of the diffraction patterns, as well as to save the life of the X-ray tube, it is necessary to strive to obtain the required information on the minimum number of diffraction patterns. The paper presents part of x-ray phase analysis method, which is successfully used in the study of structural and fuel materials.

This work presents the experimental results of structural and phase changes research study in TiN coatings under thermal and electron irradiation. Continuous electron irradiation of coated samples was performed on the ELV-4 accelerator. It was determined that electron irradiation with an electron energy of 1.3 MeV and an integral irradiation dose of 0.52·10¹⁹ e⁻/cm² leads to an increase in the microhardness of TiN coatings by 20%. It has been established that the main factor in increasing the microhardness of the coating after electron irradiation in the above regimes is the formation of new phases, in particular the intermetallide of Co₂Ti.

The paper provides findings on distribution of artificial radionuclides in aggregate fractions of soils in radioactive fallout plumes near two Boreholes – 1301 and 1077 (the former ‘Balapan’ testing area), in which underground nuclear tests were conducted that differed in the nature of the real radiological situation. In the vicinity of Borehole 1301 in which an underground nuclear explosion was accompanied by the unforeseen release of debris into the atmosphere, the highest accumulation of ¹³⁷Cs and ⁹⁰Sr occurs in 250 to 1,000 µm fractions. Distribution of ²⁴¹Am and ^239+240Pu is characterized by two different tendencies – the predominant enrichment of 250 to 1,000 µm fractions in the near zone of the plume (up to 250 m) and predominantly enriched fractions of 5–8 µm and <1 µm in the distant plume area (700 to 2,500 m). Near Borehole 1077, near which the underground explosion is assumed to have been accompanied by escaping radioactive inert gases, ¹³⁷Cs and 90Sr are mainly concentrated in less than 5 µm fractions, ²⁴¹Am and ^239+240Pu – in fractions of 8–40 µm and <1 µm.