The article provides results of the radiation survey of a 1005 km2 area in the vicinity of “Balapan” site. Earlier research into the area adjacent to “Balapan” site served as a ground for the survey thereby revealing a large-scale area of soil contamination with ²⁴¹Am. ²⁴¹Am activity concentration in soil reaches values of ~200 Bq/kg. The research result showed that such a large-scale contamination is shaped as fallout “plumes” presumably caused by atmospheric tests on the “Experimental Field” ground. A feature of this contamination is a low content of fission and nuclear activation products commensurable with the global fallout background, which is uncharacteristic of nuclear fallout “plumes” formed by aboveground nuclear tests.

The results of studying the processes of defect formation caused by irradiation with protons with an energy of 1.5 MeV and doses of 1×10¹⁵, 1×10¹⁶, 1×10¹⁷ ion/cm² in ceramics based on aluminum nitride are presented. The choice of this type of ceramics is due to the possibility of using nuclear energy as a basis for structural materials. In the course of the studies, it was found that at irradiation doses of 1×10¹⁵–1×10¹⁶ ion/cm² of ceramics showed a significant resistance of the crystal structure to defect formation, however, increasing the radiation dose to 1×10¹⁷ ion/cm² leads to a significant increase in distortions of the crystal structure and its disordering due to the effect of accumulation of defects in structure.

The PL properties of II-VI group semiconductor nanomaterials have been investigated depend of different synthesis method and other parameters. These group materials have interesting optical properties including PL properties of pure and doped materials. These group materials are mainly doped with rare earth metal for determine of improvement in the luminescence intensity. In this work we are analyzed PL properties of pure ZnS and Eu doped ZnS nanomaterials.

The paper presents the results of the study of the effect of ratios of reactive gases N₂ and O₂ on the structural phase state and the mechanical properties of nitrogen-containing titanium dioxide coatings obtained by reactive magnetron sputtering on the surface of AISI 304 stainless steel. According to the results of the X-ray phase analysis, the coatings contain titanium dioxide in the form of anatase, rutile and a small amount of brookite. It was found that with an increase in the nitrogen content in the working atmosphere, the volume fraction of anatase and rutile increases. An increase in the nitrogen content in the gas atmosphere leads to the formation of a quasihomogeneous surface texture with a less pronounced block structure. Based on the results of nanoindentation, it can be assumed that the formation of a quasihomogeneous texture can cause a decrease in the physicomechanical parameters of the coatings. It was established that the structure, phase composition, and mechanical properties of the coatings depend on the gas ratio N₂/O₂ in theт negative bias mode (U_bias = −150 V).

This work presents the results of research on the influence of electron beam processing (EBP) on the structure and mechanical properties of ultrahigh molecular weight polyethylene (UHMWPE). EBP of UHMWPE samples was carried out on an industrial pulse accelerator ILU-10. The electron energy varied in the range of 2.5–4.5 MeV, and the radiation dose varied in the range of 2–9 MGy. Thermal characteristics of polymer samples were determined by differential scanning calorimetry. The influence of irradiation on the polymer crystallization process is analyzed. It was discovered that the effect of crosslinking is not significant about the crystal structure (thickness of the lamellae) and the radiation dose almost does not affect the melting temperature of UHMWPE. The obtained infrared spectra showed that during EBP, the UHMWPE samples occur oxidation as a result of chemical reactions of the polyethylene chain with oxygen. Installed, that EBP leads to a change in the surface morphology, that is, the surface becomes rough, the depth of irregularity and the structure of spherulites increases. The results of mechanical tests showed that after EBP, the strength and hardness of UHMWPE increase slightly.

The paper is devoted to the problem of constructing nuclear power reactors based on the synthesis of light elements. This problem is currently subject to assessment under options of thermonuclear reactors operating with high-temperature plasma. In such reactors, plasma is isolated from the walls of the reaction chamber using a magnetic field. Even in advanced designs of thermonuclear reactors, temperature regime is far from the conditions for ensuring optimal interaction cross sections of the source nuclei. Despite many years of work, the task of efficient plasma isolation is difficult to solve. The size of the reaction chambers increases, predicted costs of constructing an effective reactor, even in version with the deuterium-tritium reaction, which has a maximum cross section and minimum energy of interacting nuclei. The article considers a version of the fusion reactor based on the interaction of colliding ion beams in a toroidal magnetic field. This solution provides a cost cutting to trigger the reaction, address the problem of effective retaining of interacting nuclei in the reaction chamber. An example with D–D, D–T and D–³Не reactions shows reactors based on them with low energy losses and small dimensions.

The article provides methodological approaches to research into ³Н speciation in soil. The quality and efficiency of the autoclave decomposition technique was assessed, which was used for separating bound 3Н. Soil and zeolite were used as samples for assessing the impact of the matrix structure on ³Н extraction process. In the course of the experiment, a tracer of the different activity – 100 to 100,000 Bq/l was used for assessing completeness of extraction and the impact of ³Н content. Each experiment were conducted in several replications. At each experimental stage, a blank test was conducted to assess its ‘integrity’. It was shown that the efficiency of this technique is about 27–48%. It was found that significant losses are related to an incompletely open matrix and features of the analysis carried out. It was revealed that the matrix structure and the content of ³Н do not affect the extraction efficiency of ³Н bound forms from soil. Authors suggested a number of approaches to improve the technique efficiency, such as measuring the ratio of reagents and omitting the centrifuging stage.

One of the ways of long-term handling spent nuclear fuel is storage of spent nuclear fuel in containers. For the purpose of complex radiological assessment and to make long-term prediction estimates of radiological situation possible at the territory of spent nuclear fuel storage facility the control over emanation of radioactive gases into atmosphere should be provided. Gaseous wastes are one a kind of radioactive wastes resulting from operation of nuclear energy and industry facilities. And increase in their concentration in the air indicate radioactive wastes from nuclear power plants or medical institutions, nuclear accidents and explosions and also of radiation accidents, that can include seal failure of spent nuclear fuel storage containers. Gaseous radioactive wastes include gases, containing ⁴¹Ar, ¹³⁵Xe, ⁸⁵Kr, ¹³¹I, ³Н, ¹⁴С and other radionuclides, that can often be formed and enter air environment in amounts, exceeding the levels determined by the norms of radiation safety. This paper provides results of researches of volumetric activity of gases in the air at the territory of spent nuclear fuel long-term storage facility of BN-350 reactor facility.

The article describes various methods for calculating the power of elements of an experimental device. A comparative analysis of the positive and negative sides of each methodology is carried out, methods of calculation and the limits of applicability are presented. The development of methods for calculating the energy parameters of the assembly is an important task for the development of experimental reactor physics.

The influence of parameters of iterative reconstruction algorithms used in positron emission tomography on semi-quantitative indicators and the quality of a diagnostic image in a clinical setting is investigated. The functions of the dependence of the standardized accumulation index and metabolic volume on the number of iterations are obtained. Peculiarities of the influence of iterative reconstruction algorithms on formations with a size of 6–8 mm are considered. We examined 10 patients scanned using the iterative VPHD algorithm with the PSF function turned on, time-of-flight TOF technology using the PSF function. The influence of the indicated scanning parameters on contrast, noise, and signal-to-noise ratio is analyzed. Graphs of the dependence of semi-quantitative characteristics on the number of iterations and subsets are presented. The change in semiquantitative values was estimated by varying the range of iterations and subsets. Methods for optimizing diagnostic protocols for scanning patients are proposed.

The structure and properties of proton conductors based on LaScO₃ synthesized by acceptor doping and the creation of a deficiency in La cation were studied. It has been shown that the number of intercalated protons in the oxide lattice increases with an increase in the degree of cationic doping and is higher when doped with strontium than calcium. It has been noted that in lanthanum scandate samples with cationic non-stoichiometry, the number of intercalated protons decreases with increasing lanthanum deficiency, which is probably due to the possibility of binding oxygen vacancies V_O^••  to (La_La^''' - V_O^••)' complexes and blocking their participation in the process of water dissolution. The activation energies of the conductivity of the volume and grain boundaries of lanthanum scandate synthesized by various methods are determined. It was shown that the conductivity and activation energy of conductivity of the volume of grains of samples doped with strontium are higher than when doped with calcium. It is noted that the activation energy of conductivity of samples with cationic non-stoichiometry is practically independent of the lanthanum deficiency.

The article provides an overview of existing practical methods for determining the power and energy release in fuel of fuel rods tested in research reactors. Emphasis is placed on approaches that can be successfully used in the practice of pulsed reactor tests with the unsteady character of power changes. A comparative analysis of various methods is carried out, their advantages and disadvantages are reflected. Recommendations are formulated on the application of the considered approaches in the practice of testing in a pulsed graphite reactor (IGR), aimed at studying the behavior of the fuel of nuclear power reactors in transient and accident conditions.

The article provides research findings of levels and parameters of naturally occurring (⁴⁰K, ²²⁶Ra, ²³²Th) and artificial (²⁴¹Am, ¹³⁷Cs, ⁹⁰Sr, ^239+240Pu) radionuclides accumulation by mushrooms in the territory adjacent to Semipalatinsk Test Site (STS), in the zone of fallout plume passing after the first nuclear test (August 29, 1949). It was found that, as a whole, none of activity concentration values, resulted for radionuclides in mushrooms, exceeds the permissible level. The main contribution to the total dose of internal exposure through ingestion of radionuclides, when mushrooms are consumed in the territory of interest, is made by the dose from naturally occurring radionuclides.

The paper presents data on the determination of “background” concentrations of natural (NRN) and man-made (MRN) radionuclides in the waters of the East Kazakhstan region (EKR). The objects of study were water bodies of various types: dynamic – the Irtysh, Bukhtarma, Ulba, Shar and Ayagoz rivers and static – the Bukhtarma and Shulba reservoirs and Zaysan Lake. It is shown that the concentration of NRN and MRN in the waters of EKR is 2–4 orders of magnitude lower than the values of the level of intervention established by the Hygienic standards of the Republic of Kazakhstan.

The article addresses the most common techniques for obtaining a counting sample for the alpha-spectrometric determination of plutonium isotopes – co-precipitation with rare-earth elements and the electrolytic precipitation technique. It was found that the best source for alpha-spectrometry (well-reproduced, especially thin samples with a substance uniformly distributed over the area of the active layer) is obtained by electrolytic precipitation. Optimal parameters of the process to obtain counting samples (amperage, precipitation time, geometry of an electrolytic cell) were determined for this technique and electrolyte composition was chosen. An improved electrolytic unit with highly stabilized voltage was developed and constructed.

The paper presents a methodology of a joint use of seismic and infrasound data to identify the nature of recorded events and to clarify their epicenters; the methodology is based on the search function of mutual correlation of ground truth and current records of seismic stations and further association of events-candidates with infrasound phases. The methodology was tested on materials of 7 months’ registration of industrial explosions at Akbastau quarry (Almaty region) by AS058-Kurchatov (KURK) seismic station and two infrasound stations: in Kurchatov (KURIS) and Makanchi (MKIAR); the testing showed its high reliability.

Based on the data on ground truth explosions with well-known parameters conducted in the vicinity of Almaty city, a new time-travel curve of the main seismic regional phases was built. The time-travel was compared with other velocity models, which are used for localization of events on the territory of Northern Tien Shan. It was shown that when using new time-travel curve, the sizes of error ellipse of seismic events localization are smaller than those of during the use of other time-travel curves.

he article gives research into the regional background frequency of unstable aberrations in residents of the main regions of Kazakhstan (North, South, West, East). This parameter as the dose reference “zero” point has a large percentage of uncertainty and is variable. Cities of regional importance were chosen by the biggest population size and its ethnic diversity. In each region a group of indigenous inhabitants was created – 10 volunteers in number. The groups were ranked by age and sex in the ratio of 1:1 (a total of 40 people). The background frequency for unstable chromosome damages was calculated by means of an automated cytogenetic platform on the basis of the Carl Zeiss AxioImager Z2 electronic fluorescent microscope, the automatic metaphase search and analysis system Metafer 4/M Search, ICAROS (MetaSystems, Germany). Research observations demonstrate an interregional variability of aberrant cells per 1,000 between 1.1±0.4 and 3.09±0.6, which can be attributable to a variety of human and objective factors of life activity.

The article provides summarized results on the assessment of levels and nature of radioactive contamination of the air environment with naturally occurring and artificial radionuclides (NRN and ARR) in the territory of the Republic of Kazakhstan for the typical landscape unit – a steppe zone. A technique of the theoretical assessment of ARN activity concentrations in the air is applied. It was found that the content of 40K in the air varies from 6.5×10⁻⁶ to 9.5×10⁻⁵ Bq/m³, ²²⁶Ra –2.5×10⁻⁶ to 5.0×10⁻⁵ Bq/m³, ⁷Be – 9.0×10⁻⁴ to 4.5×10⁻³ Bq/m³, ²¹⁰Pb – 1.0×10⁻⁴ to 8.5×10⁻⁴ Bq/m³, ^239+240Pu – <1.0×10⁻⁷ to 7.3×10⁻⁷ Bq/m³. Results of the theoretical assessment of showed that estimated values of 232Th volumetric activity reach 1.8×10⁻⁶ Bq/m³, ²⁴¹Am – 1.1×10⁻⁸ Bq/m³, ¹³⁷Cs – 1.4×10⁻⁶ Bq/m³, ⁹⁰Sr – 2.0×10⁻⁷. Data obtained for radionuclides background concentrations in the air is within ranges of values of international monitoring observations and can subsequently be used as basic indices for assessing variation in the quality of the air environment.

The article addresses the issue of building a radionuclide monitoring station in the Republic of Kazakhstan in order to register nuclear events and radiation accidents. Techniques for determining radionuclides in the air environment and recommendations for the choice of the main and auxiliary equipment to sample and analyze air are provided. The choice of a site for deploying the radionuclide monitoring station in Kurchatov city on the basis of NNC RK in accordance with CNTBT organization’s requirements is addressed. Data on the content of naturally occurring and man-made radionuclides in the air environment at the planned station location is given.

The paper shows an approach to performing complex design studies aimed at substantiating the required test modes of an experimental device during a reactor launch. The basis of these studies is the method of computer simulation of complex neutron-physical and thermal processes. This method based on two specialized programs MCNP6 and ANSYS Fluent.

The paper provides a pedestrian gamma-spectrometric survey technique that allows prompt determination of the concentration of radionuclides in topsoil by accumulating an array of spectra. A comparative assessment of data on the content of ²⁴¹Am and ¹³⁷Cs in soil is given, simultaneously obtained in full-scale conditions of Semipalatinsk Test Site (gamma-count rate (in situ)), and as a result of the in vitro gamma-spectrometric analysis. Transfer factors were derived based on which maps of the areal distribution of radionuclides were plotted by converting count rates to the areal activity given soil density.

The paper addresses quantitative values of the content of certain chemical elements and radionuclides in the aboveground part of sunflower in conditions of radioactive contamination at Semipalatinsk Test Site (STS). It was found that the content of chemical elements and radionuclides of interest in soil, in the same soil and climatic conditions, varies less significantly (variation factor on average does not exceed 20%) that the one in plants (variation factor is 20–40%). The widest range of activity concentration values in the aboveground part of sunflower is characteristic of 241Am, the radioactive element, which is alien to the plant body – the variation factor is more than 40%.

The article provides outputs of γ-spectrometric survey of containers containing nuclear spent fuel (SNF) of BN-350 reactor. Based upon a theoretical assessment, calculation results of dose fields of neutron and photon radiation produced by a single container with spent nuclear fuel are given, with various options of FA wall destruction and different rates of fuel fall. Initial values necessary for monitoring SNF status as well as the exposure time and a survey grid were determined. When comparing results of the theoretical assessment with experimental data, it was found that measurement points at a height of 2 m above the container bottom are optimal positions for the subsequent monitoring of SNF status in conditions of a long-term storage. These positions are the most representative and in case of fuel fall, this process will be shown in monitoring measurements.

The aim of this work was to measure the cross section of nuclear reactions natCu(p,xp) on the isochronous cyclotron U-150M of the Institute of nuclear physics at the energy E_p=7 MeV. The analysis of the experimental results of these reactions on the natCu is carried out in accordance with the exciton model of nuclear decay, which is a statistical approach describing the transition of the excited core to an equilibrium state. The theoretical analysis of the experimental results was performed in the framework of the PRECO-2006 calculation code. The obtained experimental results can be used in the design of hybrid nuclear power plants, as well as in radiation materials science.