The paper presents theoretical and experimental data determining the effect of acoustic perturbation on the readings of
a γ-detector (CGS) with a working medium (high-pressure xenon gas) operating in the field of ionizing radiation. For this purpose, a chain of events is considered: an acoustic wave falls on the surface of the CGS, passes through and produces a perturbation in the gas which forms a non-uniformity of pressure distribution in the working medium. Exposure to ionising radiation leads to the formation of positive ions in the gas, the mobility of which is much lower than the mobility of free electrons, which are the main carriers in CGS. The experiments are carried out using an unmanned dosimetric complex BDK with a carrier in the form of (helicopter-type UAV) on which dosimetric equipment used for radiation control of the environment in conditions of its radioactive contamination is attached. Theoretical results obtained by solving the wave equation of sound wave passage in xenon filling the CGS are presented in the form of xenon density. The obtained data allowes us to obtain the radial distribution of the current density at different moments of the harmonic acoustic oscillation period. Experimental data demonstrated frequency characteristics of acoustic load and their amplitude values in different modes of UAV operation. The results of the research determine the recommendations that should be taken into account when using UAVs as carriers of dosimetric equipment in radiation monitoring of the environment. 

The paper analyses contribution of reactions (n,X) and (p,X) on nitrogen and oxygen nuclei to the production and transfer of cosmogenic tritium in the Earth atmosphere. To calculate the fluxes of secondary protons and neutrons in the nuclear-electromagnetic cascade, the analytical model «PARMA» was used. The model is based on analytical approximations of both numerous experimental data and computer simulation data, and allows one to calculate the fluxes of various particles of secondary cosmic radiation (nucleons, muons, a- and b-particles) with the choice of a given energy range, atmospheric height, geomagnetic cutoff rigidity, solar activity. The problem of vertical turbulent diffusion of tritium in the Earth's atmosphere was solved and the dependence of its concentration on altitude was obtained. Numerical integration of the transport equations was carried out using the integro-interpolation method. An estimate of the total reserve of cosmogenic tritium in the Earth's atmosphere, balanced by turbulent diffusion, decay and cosmogenic formation, was given, which amounted to ~1.9∙10¹⁷ Bq. The calculation results show that the earth's atmosphere contains no more than 10% of all cosmogenic tritium. The results are generally consistent with earlier empirical and semi-empirical models confirming that man-made tritium currently accounts for the majority of the total tritium supply

Radioecological monitoring of natural and urban areas is intended not only to assess the consequences of the operation of nuclear fuel energy enterprises, but also to ensure radiation safety of humans and the environment. This type of research allows not only to identify areas with increased background radiation, but also to reduce social tension in the population associated with radiophobia. This paper presents the results of long-term studies of the ambient dose equivalent rate (ADR) of gamma radiation within urban and rural settlements of the Southern Federal District using the example of the Krasnodar Territory. ADR measurements were carried out at a height of 100 cm from the earth's surface using dosimeters-radiometers SRP-88n, DRBP-03 and DKS-96s with a detection unit BDKS-96s using pedestrian gamma survey methods. The study regions represent different types of landscapes: steppe plain territories, the foothills of the North Caucasus and the Black Sea coast. It is shown that the arithmetic average ADR values in urban conditions are 0.11 μSv/h, and in rural settlements – 0.14 μSv/h. Similar results may be due to differences in soil and climatic conditions in different settlements. In general, differences in gamma radiation ADR may be due to a greater extent to measurement uncertainty (standard deviation), and also, to a lesser extent, to relief features and the content of radionuclides in the soils of a given region. The radiation situation in the Krasnodar Territory at the time of the study complies with the requirements
of SanPiN 2.6.1.2612-10. The gamma radiation equivalent dose rate values are within the limits of natural background fluctuations characteristic of the Russian Federation.

The introduction provides an overview of scientific research on the sources of generation, characteristics and classification of infrasound. It is noted that infrasound has a number of features related to the low oscillation frequency of the elastic medium and the diffraction property. Infrasound has harmful effects on hearing, breathing, vision, gastrointestinal tract, nervous and cardiovascular systems, brain and vestibular apparatus, leading to decreased performance, general malaise and premature aging of the human body. The methodology of theoretical substantiation of methods for detecting previously unknown sources of infrasound, improving the environmental, radiation and industrial safety of nuclear power plants with WWER-1200 is based on the use of digital acoustic models of primary circuit equipment responsible for operational safety developed under the guidance of K.N. Proskuryakov. The methodology of practical confirmation of the results of computational and theoretical forecasting of acoustic parameters of previously unknown infrasound sources is presented in the form of two stages: a) development of a methodology for verifying forecasting results and selection of power units No. 1, 2 of Novovoronezh NPP-2 in the form of objects; b) investigation of the conditions for the occurrence of vibro-infrasound resonances in the first circuit. The developed method for investigating infrasound sources has been verified at the WWER-1200 reactor plant. When discussing the results of the conducted research, previously unknown sources of infrasound were identified. Innovative methods of analysis and damping of infrasound sources have been developed and a patent for invention No. 2803181 «A method for preventing resonant interaction of vibrations of water-water power reactor equipment with acoustically standing waves and a device for its implementation» has been obtained. The errors of the chief designer of reactor installations with WWER in the regulations for the launch of new power units are noted; their negative consequences for the health of personnel and the condition of equipment responsible for environmental, radiation and industrial safety of nuclear power plants with WWER are indicated

Evaporation plays an important role in maintaining water balance and managing water resources in reservoirs. This problem is relevant in hot regions with a lack of fresh water. In addition, reliable operation of evaporators plays an important role in preventing overheating and ensuring safe cooling of reactors which is critical to maintaining nuclear safety. The complete control and accurate measurement of the evaporation process provided by the developed device enables efficient water management ensuring the stability of nuclear power plants and minimising environmental risks. Evaporators are used to control the evaporation process in reservoirs. Based on the analysis of existing evaporators and their shortcomings, an evaporator with horizontal plane stabilization in the pan is developed. Due to this function the developed device allows to control the evaporation process with higher accuracy by reducing fluctuations in the water level in the evaporator. The developed device contains an autonomous power supply that uses energy-saving technology based on a solar battery which ensures operation without additional sources. The use of such a power supply increases the evaporator reliability. One of the important advantages of this device is the use of a cellular-based information transmission channel to the control center which allows to transmit the results of evaporation quickly monitoring and make water management decisions accordingly. In addition, the use of a GPS navigation system allows to set or determine the coordinates of the evaporator installation in the reservoir accurately. The developed device can be included in an intelligent energy resource management system; its use will significantly improve the safety and sustainability of nuclear power plants by improving evaporation process control. It will also optimize the nuclear power plants operation, promote efficient management of water resources and ensure safety in the nuclear energy field.

Due to the variety of defects that arise in electrical machines, it is necessary to use more effective methods for monitoring their condition. All over the world research and development of new means and methods for monitoring powerful electrical machines during their operation is underway. Some examples of recent advances are vibration diagnostic methods for assessing the compaction of components inside a transformer, acoustic and electrical systems for monitoring partial discharges, data processing using digital methods, and new sensors for continuous monitoring of gases and moisture in oil, as well as hot spot temperatures. Additionally, thermal imaging testing of power equipment is also an important tool to ensure reliable operation. It is believed that the most effective method is gas chromatographic oil analysis, which can identify most defects in oil-filled equipment. During the operation of powerful electrical machines, the use of existing non-destructive testing methods does not allow a complete assessment of the condition of the main parts of the equipment, as an analysis of damage locations shows, 25% are damage to the core and windings. Effective monitoring of the condition and determination of the performance of transformers is of particular importance, since they are key elements in the operation of nuclear power plants. The paper considers the possibility of using the eddy current testing method; determining a defect in magnetic core steel is based on fixing the unevenness of the magnetic field on the horizontal or vertical planes of a yoke or rod consisting of electrical steel plates. Monitoring and evaluating the functioning of existing equipment, detecting deficiencies in the early stages of their development, when repair costs are still minimal, and preventing emergency failures become a priority. In accordance with the growth rate of detected deficiencies, monitoring is carried out from time to time or continuously, the maximum number of monitored characteristics is achieved when the transformer is fully tested to determine its functionality.

During the operation of NPP steam pipelines the main damaging factors are not only corrosion and erosion leading to thinning of the pipe wall but also fatigue damage resulting not only from temperature self-compensation efforts, but also high vibration load. As practice shows, the most promising direction of ensuring the vibration resistance of steam pipelines at present is the computational and experimental study of the stress-strain state of pipelines under vibration loading. This work shows that the strength of the most commonly used standard sizes of steel pipelines under the influence of vibration loads is determined in accordance with Russian State Standard R 59115.9-2021. Taking into account the stress concentration, the amplitudes of the conditional elastic reduced stresses were determined for the 4 variants of the calculation schemes accepted for consideration. The permissible amplitude of stresses from an operating condition of 60 years is determined. It is shown that the permissible voltage amplitude for the design temperature t = 350°C will be no more than 46.4 Mpa for a pipe made of 12X18H10T. As for NPP pipelines, the normalized vibration parameters in the regulatory documentation were not established until 2022, when the following vibration velocity limits were adopted for pipelines of nuclear power plants in Russian State Standard R 59115.11-2021, vibration resistance testing is not required: nmax up to 15 mm/s, nmsv up to 7 mm/s. Thus, currently in the Russian regulatory documentation there are no normalized values of vibration parameters (as a rule, vibration velocity) for pipelines selected depending on the frequency of vibration exposure. It is proposed to develop and introduce into the regulatory documentation frequency-dependent criteria for limiting vibration parameters of NPP pipelines, specified in accordance with the actual operating conditions of these pipelines.

The article examines the problem of forming scientific and technical programs for the conversion of research nuclear installations at the decommissioning stage, which arose in the aspect of justifying the possibility of extending the designated service life of all existing research nuclear reactors in Russia. To solve this problem, a methodology is proposed, which includes an information model and a process description of the necessary step-by-step actions, as well as a set of appendices in the form of documents justifying the most optimal ways to form a project for managing the quality of nuclear reactor conversion processes in relation to special life cycle conditions of specific nuclear reactors. The general view of the methodology is described: principles and methods of construction, structure. An example of the application of this technique in the conversion of the Hydra salt solution pulsed research reactor for the decommissioning stage is given. The purpose of the conversion of the Hydra reactor is to extend the designated service life by replacing non-repairable equipment ­ the vessel. The main criteria for justifying the residual life of the housing are formulated, which are the presence of a safety margin of the housing material, taking into account the accumulated fluence on more vulnerable areas and the justification of the integrity and tightness of the housing. For clarity, the conceptual information model of the methodology for justifying the safety of the process of replacing the Hydra reactor vessel is presented in the form of an Ishikawa diagram. The methodology represents a series of sequential scientific and technical activities, research and a finite number of step-by-step actions to achieve the final goal – extending the service life. The stages of the methodology for justifying the safety of replacing the Hydra reactor vessel are described, such as «clarification of initial data», «performing computational studies and laboratory experiments», «clarification of the requirements of methodological documentation» and «formation of a work plan» and «registration of licensing documents for operation».

The objective of the study is to show the significant impact of taking into account the actual values of residual stresses on the strength and resource of safe operation of nuclear power facilities. Generally accepted approaches of strength physics and fracture mechanics were used to determine strength and service life. The degree of influence of residual stresses on the strength and service life of pipeline elements in the case of a cyclically acting load, under static load, when there is a danger of brittle fracture, and in the case of corrosion is investigated. The objects of the study were pipelines of nuclear power plants. It is noted that the current state of science and technology has made it possible to create a technique for non-destructive testing of mechanical stresses acting in metal structures based on the use of the acoustoelasticity method. Currently, on the basis of this method, a method for measuring residual welding and installation stresses in pipelines has been developed and certified for use in the field of atomic energy use. The measurement technique provides for the determination of membrane and bending stresses in annular sections located on rectilinear sections of pipelines. The values of stresses in the structural elements of pipelines and residual welding stresses in the deposited metal of welded joints are determined using ratios based on the use of the balancing principle. The relevance of introducing into the procedure for monitoring the technical condition of pipelines and equipment of nuclear power plants the procedure for determining the actual level of residual stresses, which significantly increases the reliability of the assessment of their strength and service life, is shown. It is proved that in order to implement the procedure for determining the actual level of residual stresses, it is necessary to use a non-destructive testing system for residual welding and installation stresses using the acoustoelasticity method based on a measurement technique that allows determining the actual values of residual stresses with established error characteristics.

In a WWER-type pressurized water reactor, high-neutron-absorbing materials can compensate for the excess reactivity. Theoretical and computational analyses were conducted in this article to use burnable absorbers placed in a fuel rod to reduce the reactivity margin for extending refueling time for WWER-type reactors. To investigate the reduction of the reactivity margin, the fuel burnup calculation was performed without a burnable absorber and with a combination of a variety of burnable absorbers, namely natural Gadolinium (Gd) and Erbium (Er), applying a simplified GETERA program. The calculation found that the variation of the quantity of the burnable absorber (Gd, Er) inside the fuel assemblies governs the reactivity margin for the fuel burnup and increases the efficiency of Uranium fuel (UO₂). The combined use of Gd and Er leads to a smoother decrease in reactor reactivity due to a smaller Er absorption cross section, which makes it possible to reduce the total mass of Gd in the fuel element and reduce the blocking effect. In the calculation, Gd concentrations employed in the computation at 1.5% and 3%, while Er concentrations were used within the range of 0.1%–0.6%. 

The paper examines the issues of optimizing the operation of the rotation mechanism of the television rod of the refuelling machine during the refueling campaign during the scheduled preventive maintenance at the NPP. The task under consideration is to minimize the time spent on turning the television rod during a reloading campaign in order to save time and money on technological operations, and thereby reduce the downtime of the nuclear power plant unit. A description of the design and purpose of the work area, the refuelling machine and other objects involved in technological operations is provided. In all parts of the working area there is a certain number of «problem» cells in which interference and/or blocking of rotation of the television rod may occur. The exact location of all «problem» cells and the permissible angles of movement and observation for them are revealed. The list of operations is compiled as a table containing: operation numbers, markings of the corresponding cluster, as well as the initial and target positions in coordinates. This table comes complete with a cartogram with coordinates and cell labels. It is calculated how long it takes to turn from one permissible viewing angle to another. An example of time calculation for an operation with a reloading machine is given.

Determining the minimum required cooling time of profiled assemblies at the Armenian Nuclear Power Plant, taking into account the load schedule, is an analytical process to establish the shortest required period during which profiled assemblies used in the nuclear power plant energy process must remain in active use. This process considers factors related to changes in the electrical load on the station during different periods. Within the scope of this definition, an analysis of the technical characteristics of profiled assemblies is conducted as well as their impact on the overall performance of the nuclear power plant. Key considerations in the cooling time include operational safety, compliance with regulatory requirements, and efficient distribution of energy resources in accordance with the load schedule. The goal of this process is to ensure optimal and safe operation of profiled assemblies, adapted to changes in the electrical grid and aligned with the load schedule, thereby contributing to the more efficient functioning of the nuclear power plant. This study aims to substantiate the minimum required cooling time for profiled nuclear assemblies characterized by an average uranium enrichment of 3.82% and an average burnup of 45.7 Megawatt-days per kilogram of uranium (MWD/kgU). Calculations are performed using the ORIGEN-ARP program, part of the SCALE software package designed for the analysis and modeling of radioactive and nuclear processes. The study considers parameters such as the composition of nuclear assemblies, fuel burnup, modeling using the ORIGEN-ARP program, and safety analysis. The results obtained aim to make a significant contribution to enhancing the efficiency and safety of nuclear energy installations

As the object of research in the paper practical solutions in terms of material and non-material incentives for personnel in energy companies as well as methodological guidelines justifying their implementation are chosen. The subject area chosen is the processes of personnel motivation in energy companies in Russia. The objective of the study is to formulate directions for improving this work based on the analysis of information presented in the open press about existing approaches to building a system of personnel motivation in energy companies, taking into account modern transformations in the industry and the demand for innovative development. The methods used in this article include theoretical analysis of scientific literature on personnel motivation in relation to the development of the energy sector, graphical method, analysis of statistical data, analysis of documents covering decisions on personnel motivation in energy companies and the application of advanced digital technologies in management. The main result of the study is the conclusion that the basis for the development of the motivation system should be the perception of employees not as one of the company's resources, but as its value asset, the growth of their involvement for the benefit of achieving the goals and objectives which implies a change in the approach to the personnel motivation system, namely, the strengthening of the personalised component. This approach will allow to focus on incentives, tangible and intangible, oriented to each specific specialist, according to his/her role, contribution and prospects for the organisation. Tangible non-monetary incentives may (with equal amounts in terms of monetary equivalent) differ depending on the employee's interests, his/her needs (education, sports, examinations, hobbies, etc.) and the needs of their family. Non-material incentives related to the formal and informal status and personal brand of an employee in the organisation should also be individualised. This implies the use of AI to process an array of information about existing employees and determine their real contribution to the company's development, their performance at their current place of work, and to develop individualised motivational proposals with subsequent measurement of their performance.

The object of research in this article is the «Atommash» the branch of «AEM-Technologies» JSC in Volgodonsk, an organisation that was designed and commissioned in 1976 as the head machine-building enterprise for the production of a complete set of hull and heat-exchange equipment for NPP power unit in the volume of the nuclear island. The subject area chosen is the organisation of production of large-size products, which the enterprise intends to diversify through the acquisition of a line for the manufacture of thin-walled bottoms of large-size pressure vessel housings for NPPs and oil and gas chemistry. The purpose of the research is to develop a project for the development of new technological capacities based on the analysis of existing technologies and methods of production, which will increase the efficiency of production activities at the «Atommash» the branch of «AEM-Technologies» JSC in Volgodonsk. The main methods in writing the article were theoretical analysis of scientific literature on the research problem, graphical method and study of local documentation of the research object in terms of modernisation of production facilities. The main result of the research is the conclusion about the necessity of introducing a new technology – cold rolling (flanging) in order to expand the technological capabilities of the enterprise, to increase the efficiency of production in this area, to gain profit from the supply of thin-walled vessel bottoms to other enterprises to replace European suppliers, and as a consequence an increase in competitive advantage.