This study considers the possibility of using high-energy electrons (3.8 MeV, dose range of 46–200 kGy) for radiation-induced grafting of the polyethylene terephthalate ion-track membranes (PET ITMs) with the functional monomer of acrylic acid (AA). The effect of such factors as monomer concentration, dose, and average speed of the beam section of the accelerator conveyor was studied. The pristine and grafted samples of ion-track membranes were comprehensively studied by advanced physicochemical techniques. As a result of the studies, the optimal conditions for the radiation-induced grafting of PET ITMs with accelerated electrons were determined. A sufficiently high degree of grafting of AA while maintaining the mechanical strength of the polymer template were achieved for next conditions: the content of CuSO4 inhibitor is not more than 1%, the acrylic acid monomer concentration is not more than 10%, radiation dose in the range of 100–117 kGy.
Beryllium has been widely used in nuclear power engineering. In this case, it refers to rare metals, since its content in the earth's crust is ~ 510−4 %. A small prevalence in nature, a complex technology of extraction from ore and obtaining products determine its high cost [1]. In the process of using beryllium in nuclear power, various radionuclides accumulate in it, which limit its reuse. According to this, the problem of purification of irradiated in a nuclear reactor beryllium from radionuclides is topical.
The article discusses the principle of operation and the composition of the equipment of the direct flow irradiated berillium chlorination plant. This technology involves the conversion of beryllium and its radionuclides to chlorides, followed by their separation. The final product is beryllium chloride in liquid form
The results of modeling the effects of molten steel and ceramic nuclear fuel (uranium dioxide) on the steel wall are presented. The duration of the process until the formation of a through hole in the steel wall and the amount of melt that is necessary for this are estimated.
Research of thermophysical features of the process of protective pyrocarbon coating application on a coated particle fuel model in the fluidized bed reactors was carried out in Gas Institute of the National Academy of Sciences of Ukraine.
Based on thermodynamic calculations, the optimal thermal parameters of the process of protective pyrocarbon coating application to models that, due to their physicochemical characteristics, are the closest to coated particle fuel (Dy2O3, Gd2O3, Sm2O3, SiO2) were determined.
As a result of a series of experiments on specially developed laboratory facility with electrothermal fluidized bed, samples of models of coated particle fuel coated with pyrocarbon were obtained.
The dynamic characteristics of the discharge current in a thermonuclear plasma focus installation and its dependence on neutron emission was studied. The dynamics of the formation of discharge pickcurrent was measured and analysed through the Rogowskiy belt and activated neutron flux with an activated silver foil detector. According to the results of the analysis, the discharge peak current at a voltage of 18 kV from 200 to 265 kA and the pinch current was varied depending on the pressure between 178–230 kA. Accordingly, the neutron flux was 8·106–2.2·107 neutron/imp. The dependence of neutron emission on discharge pinch current in plasma focus device installation is described.
The study determined the physico-chemical parameters for the production of cellulose from the husk of sunflower seeds. The yield and chemical composition of the obtained cellulose were determined, the chemical structure was studied with IR spectroscopic method, the morphology of a scanning electron microscope, and the crystal structure was studied with X-ray diffractormeter.
n this work the peculiarities of formation ultrathingrained structure and regularities of mechanical properties improvement of aluminum alloy AMЦ, processed by equal channel angular pressing (ECAP). A systematic study of changes in the structure and mechanical characteristics (microhardness and wear resistance) of the AMЦ aluminum alloy, depending on the number of passes and the angle between the pressing channels at the ECAP. The work shows that by varying the number of passes, different grain sizes and different values of mechanical characteristics can be obtained. It was found that with a decrease in grain size, the microhardness of the AMЦ alloy increases by 4.5 times compared to the initial state. It is shown that after ECAP-12, the mass loss decreases, which shows an increase in the wear resistance of the AMЦ alloy by 13–14%. It was identified that after the ECAP of the AMЦ, the strength characteristics increase, and the plasticity decreases when the transition to the ultrathingrained state.
The studies described in this paper are devoted to the study of helium and tritium release formation in the solid phase state of new Li15.7Pb lithium-lead eutectic under irradiation. The paper describes the main properties of the new material and its microstructure. The comparison of microstructures of eutectic Li15.7Pb and Pb17Li is given. Helium and tritium free path length in the near-surface layer of the lead lithium eutectic sample were calculated. The rate of helium and tritium formation in this material during its irradiation at the IVG.1M reactor has been determined. Estimation of helium and tritium release formation from the near-surface layer of the Li15.7Pb lithium-lead eutectic has been done and a comparison with experimental data obtained in in-pile test has been presented.
The results of a comparative cytogenetic and morpho-biological study of indicator groups of animals living in the territory of the Altyn-Emel National Park and in the area of the preserved Suluchekinsky uranium deposit (Almaty region, Kerbulak district), where the experimental extraction of uranium by the UBL technology (Underground borehole leaching technology). In accordance with the indicators of EDR (equivalent dose rate γ – µSv/h) and surface alpha activity (α – part./min·cm2) for the entire territory of the deposit and adjacent surveyed areas, no area radioactive contamination has been established. However, in the circuit of the Kalkan seismic well borehole , the DER values are determined in the range (0.462–4.158 µSv/h), which exceed the standards. For indicator animals (fish and amphibians) living within the boundaries of the deposit, an increased level of cytogenetic disturbances (micronuclear test in fish) and anomalies of the oral apparatus in tadpoles of toads of the Bufotes viridis complex are observed.
The paper addresses issues of providing the representative experiments with fuel rods of fast reactors in central experimental channel of the IGR thermal pulse reactor. Preliminary calculations demonstrated a possibility to receive quite intensive field of fast neutrons in the IGR using converters of various designs. For a shift to such tests of fuel rods of fast reactors in the IGR, experimental substantiation of calculation studies is required. It was suggested to implement the experimental substantiation using a set with two types of fuel rods, one of which operates in thermal spectrum of neutrons and another one – in a neutron spectrum obtained using the converter. The design of such an experimental device has been developed; its performance has been calculated. The safety justification for its testing in the IGR has been carried out.
This article gives results of the developed multimedia, geoinformation web-site “Radioecological interactive atlas of Semipalatinsk Test Site”. An interactive atlas is an electronic map that operates in the mode of two-way human (user) and computer dialogue interaction and represents a visual information system. The interactive atlas provides the official historical information on nuclear tests conducted at STS and up-to-date information on the current radioecological situation in the entire STS ecosystem (soil cover, air basin, groundwater, flora and fauna, surface water bodies (STS). This development is aimed at providing different users with information on STS.
The article shows the possibility of applying a simulation experiment to obtain representative values of the accumulation of artificial radionuclides by agricultural products the case of Lactuca sativa culture. The experiment used soils from areas of Semipalatinsk Test Site (STS) different in type and nature of radioactive contamination. Transfer factor (Tf) were derived for artificial 137Cs, 241Am, 90Sr and 239+240Pu for Lactuca sativa. A comparative analysis was carried out for Tf of radionuclides in STS areas with a different nature of radioactive contamination.
The paper provides results of radioecological survey of the site «4» at the territory of Semipalatinsk Test Site, where warfare radioactive agents were tested. Pedestrian gamma survey and discrete gamma-spectrometric survey was carried out at the territory researched, and also quantitative and qualitative radionuclide composition of soil was determined. 9 new radioactively contaminated areas were discovered.
The paper is devoted to the problems of synthesis reaction physics of light elements. In this area, experimental data and models of nuclei interaction processes created on their basis play an important role. Quite accurate experimental data on the interaction cross sections have been accumulated, approximation formulas have been obtained that describe dependences of the cross sections of a number of reactions on nuclear collision energy. However, creation of models that describe in detail the progress of reactions encounters such difficulties as complexity to describe problems with many variables, difficulties of obtaining reliable experimental data on the scale of nuclear interactions. This paper provides an attempt to describe the synthesis processes in the D−D, D−Т, D−3He, Т−Т и 3He−3He reactions based on the possibility to separate interacting nuclei into quasi-free fragments. Three leading fragments in these reactions were revealed. The calculations of the cross sections based on these representations gave interesting results. Areas of action of nuclear forces in these reactions were determined.
In 2019 members of the “Institute of Atomic Energy” branch of RSE NNC RK carried out work on Information and Management System (IMS) development for “KORINA-2” facility. Tasks were defined, solved as a result of indicated project implementation, data processing algorithms from primary converters, methods for information visualization and presentation on operator’s display screen were developed. The outcome of this work was a system, in which functions such as measurement, calculation, management, registration and display of experimental information at “KORINA-2” facility were implemented.
The results of the short-term thermal tests of SFA samples in the temperature range 450–900 °C are presented. The dependences of the formation of the corrosion layer of the SFA material on the temperature of thermal tests are determined by various ways. It was found that with an increase in the temperature of isochronous exposure above 750 °C, a noticeable discrepancy appears between the dependencies determined by various methods, due to the occurrence of uneven (localized) corrosion.
The WWR-K reactor is a unique 6 MW multi-purpose light-water research reactor. Desalinated water is the coolant and moderator, and beryllium is the reflector. Uranium dioxide enriched up to 19.7% on the uranium-235 isotope serves as fuel. Since the launch of the WWR-K reactor, studies of various materials of research reactors have been carried out on it. Beginning in 2000, work was carried out at the WWR-K reactor to study the materials of fusion reactor, namely, experiments to study the release of tritium from lithium ceramics. A facility was developed for in-pile reactor studies of tritium release from various candidate materials for a breeder blanket of a fusion reactor in an inert gas environment. A methodology was also developed for estimating the retention time of tritium in irradiated materials. In 2018, an installation for studying the materials of fusion reactors was created at the WWR-K reactor, at which it became possible to conduct experiments on irradiating samples in a vacuum. In this work, a description of the WWR-K reactor, experimental facilities, and their general technical capabilities as applied to the expected studies of tritium yield from the fusion reactor materials at the WWR-K reactor is presented.
This work is devoted to the study of changes in the structural and phase states of TiCN coatings on the surface of titanium synthesized by mechanical fusion. In the work influence of heat treatment on the structural-phase states and mechanical-tribological properties of coatings was studied. It is established that the mechanism of formation of TiCN coatings is conditioned mechanical cold welding due to the deformation compaction of powder particles on the surface of titanium under the influence of ball impacts. The influence of heat treatment on the structural and phase states of TiCN coatings is studied. It is shown that at temperatures of 600 °C and 900 °C for 2 h, the TiCN coating is thermally stable. Microhardness and wear resistance of coatings have been studied using methods microindentation and tribological tests. It was found that at 900 °C, the wear resistance and microhardness relative to the initial increases twice, while the adhesive strength of the coatings does not deteriorate.
To determine the effect of Cr2N coating on the performance of rolling bearings, this article has studied the tribological and corrosion characteristics of thin-film coatings obtained by the MF method. The tribological characteristics of coatings were studied using the “ball on disk” scheme before and after Cr2N coatings were applied. As the counterbody was used a ball of SchCh15 (without coating). Analysis of cross-sections of wear tracks after testing indicates that there is virtually no wear after coating. The coated sample has a coefficient of friction of 0.14 0.17, i.e. it does not exceed the value of the coefficient of friction (<0.2) required for materials in dry friction pairs. The method of potentiometry was used to determine the corrosion of steel SchCh15 before and after applying a thin-film coating Cr2N.Corrosion tests were performed on a potentiostat-galvanostat P150, in a 4% solution of nitric acid (HNO3). The test results showed that after applying the Cr2N coating, the corrosion rate was 0.191 cm/year, i.e. half as much as that of uncoated steel SchCh15.
This work is devoted to the development of a methodology for conducting reactor experiments to study the interaction of hydrogen isotopes with lithium CPS by the dynamic sorption method. As a result of the work the design of an experimental irradiation device for conducting reactor experiments was developed. Neutron-physical and thermophysical calculations were performed to justify this design for use in reactor experiments. A technique was developed for conducting experiments with a sample of lithium CPS as a result of which the methodological conditions of the tests were determined: sample temperature; levels of deuterium flux supplied to the experimental cell; sample size; sample pretreatment conditions; system pump out mode, sample temperature adjustment mode, mass spectrometric measurements of the gas composition above the sample. Methodical experiments were carried out to determine the temperature dependence of the gas composition change in the chamber with a lithium CPS when various deuterium flows were applied. Thermal desorption experiments with a sample of lithium CPS were carried out.
During past several decades PL properties of II-VI group semiconductor binary compounds have been investigated. These group materials are doped with rare earth metal ions for determine of improvement in the luminescence intensity. In these review article look over influence of different parameters of PL properties of pure CdS nanomaterials and doped CdS nanomaterials.
ISSN 1729-7885 (Online)
