The importance of implementing automated wastewater monitoring systems is growing as environmental responsibility requirements for nuclear energy become increasingly stringent. This article considers the rationale and practical implementation of an automatic continuous wastewater monitoring system (SAİS) using the Akkuyu NPP as a case study. The regulatory foundations are described, including international IAEA recommendations and the environmental legislation of the Republic of Turkey, as well as the methodological approach to system design. The main sources of potential impacts of NPP discharges on the marine ecosystem are analyzed, and the necessity of continuous monitoring is substantiated. Key technical characteristics of SAİS are presented, including its architecture, measurement circuits, and data transmission tools. Special attention is given to metrological support and quality assurance of measurements. It is noted that the implemented system ensures continuous monitoring of key wastewater parameters, reliable real-time data transfer to the centralized database of the supervisory authority, and legally binding recording of environmental indicators. A comparative analysis of the Turkish approach to online monitoring versus the Russian practice of laboratory-based control is provided. The advantages of SAİS as an instrument of digital transformation in environmental monitoring are discussed, along with the potential for scaling this experience to nuclear power plants in Russia. The study concludes that automated monitoring is essential for improving transparency, reducing environmental risks, and strengthening public trust in the nuclear industry.

The principle of optimization is of great practical importance for ensuring the radiation safety of personnel at all stages of the NPP life cycle, especially, newly designed nuclear power plants. In 2007, the International Commission on Radiological Protection (ICRP) issued recommendations (Publication 103). The recommendations further reinforce the importance of optimizing radiation protection by disseminating successful experiences in implementing this requirement in practice, now including situations of planned exposure. The consistent policy pursued by the operating organization of Russia's nuclear power plants (Rosenergoatom Concern) has been pursuing a consistent policy to introduce and implement a methodology for optimizing radiation protection at all nuclear power plants since 1996 (transition to new dose limits), which has led to a reduction in collective radiation doses for personnel by approximately four times. Areas for further optimization of radiation protection for personnel are determined by individual dose management (improving work organization, improving the radiation environment, reducing time spent in dose fields). The objective of the work is to develop a software system that allows the creation of personnel movement routes with minimal total dose exposure in rooms with heterogeneous radiation fields. The following tasks are accomplished to achieve the goal: analysis of the safety movement problem in radiation-hazardous areas; construction of a mathematical model of the radiation field using the radial basis function (RBF) method; development of pathfinding algorithms taking into account dose load (A*, A-star, dynamic programming). The article presents problem solutions using mathematical route optimization methods that minimize personnel dose costs in relation to a real radiation-hazardous room at a nuclear power plant. The main stages of developing an algorithm that automatically generates optimal routes, taking into account the heterogeneous radiation environment in the space, the size of the room, and the location of equipment and other elements within it, are described. The scientific novelty of the research lies in the application of the radial basis function (RBF) method in combination with graph routing algorithms adapted to the radiation dose minimization criterion, as well as in the use of a modified Bellman equation for the optimal selection of the order of passing control points.

This paper presents the results of numerical modeling of the VVER-1000 benchmark with a mixed loading of uranium and MOX fuel, developed by the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (NEA OECD), using the OpenMC code. OpenMC is a Monte Carlo-based neutron transport simulation code that employs Python as a user interface. The neutron cross sections for various nuclides required for the calculations are obtained from the ENDF/B-VII.1 and ENDF/B-VIII.0 evaluated nuclear data libraries. The use of two different nuclear data versions made it possible to assess the sensitivity of key neutronic parameters of the VVER-1000 reactor to the choice of cross-section libraries. Calculated values of the effective multiplication factor and fission reaction rates in the fuel assemblies for several stationary reactor states are compared with benchmark results obtained using MCU, RADAR, and MCNP codes (published by the NEA OECD and, in particular, by researchers from the Turkish Atomic Energy Authority). Additionally, a cross-verification of the results is carried out using an independent model of the VVER-1000 benchmark developed in the Serpent code. The results demonstrate good agreement with other high-precision codes and confirm the correctness of the OpenMC and Serpent models. The presented methodology is applicable for further modeling and analysis of new core configurations in various reactor systems

The article discusses the actual problem of automating the diagnostics of nuclear power plant equipment to improve its reliability and safety. A method for detecting leaks in pipe fittings based on the use of artificial neural networks for the analysis of thermographic images is proposed. The methodology is based on thermal imaging control, which allows remote and contactless recording of temperature distribution on the surface of the equipment. Based on a limited set of initial thermographic images, a convolutional neural network is created and trained for binary classification of equipment condition (presence and absence of leaks). The trained model demonstrated 100% accuracy on the test data. The developed approach makes it possible to automate the diagnostic process, eliminate the influence of the human factor and can be integrated into predictive maintenance and real-time monitoring systems.

This paper describes a unique experience in cleaning the sprinkler of the evaporative cooling tower at power unit No. 1 of the Novovoronezh NPP-2 to increase its cooling capacity. The effectiveness of reagent cleaning of the sprinkler from carbonate deposits during the 2025 repair campaign was evaluated in comparison with mechanical methods tested earlier. The process of reagent interaction with contaminants is described. The influence of the working solution on the structural elements of the cooling tower is considered. Particular attention is paid to the cleaning technology with an emphasis on safety, technique, and quality of work with the achievement of process success criteria. The results of laboratory tests to determine the chemical composition of deposits and final cleaning products are presented. Methods for the disposal of wash water with minimal environmental impact are proposed. The article analyses the influence of process factors on its effectiveness: composition, reagent concentration, exposure time of the washing solution, and the degree of contamination of the sprinkler areas. The economic effect and payback period of the presented method are calculated based on the data obtained on the change in the cooling capacity of the cooling tower after SPM-2025.

For the first time, the article raises the problem of the possibility of using the high-frequency component of neutron noise to monitor the state of fuel assemblies and fuel rods during operation, since for long-time neutron noise research was limited to a frequency of 50 Hz. A brief historical summary presents the main points and stages of the development of neutron noise control, as well as the personalities of individual scientists who have made fundamental contributions to the development of neutron noise diagnostics. Using the example of data from the Novovoronezh NPP obtained during dynamic tests in 2022, the authors show the possibility of estimating the natural fluctuations of the control bodies of the control system as a function of frequency-depth of immersion in the core. This dependence makes it possible to build an alternative channel for monitoring the position of the regulatory authorities. Based on spectral estimates of high-frequency neutron noise, the possibility of detecting the boiling mode of the coolant with localization of the location by the height of the fuel assembly is substantiated. For the first time, data (frequency composition) on possible natural fluctuations of fuel rods (parts of fuel rods) measured directly during operation is presented. These values are given in the form of specific values, and not in the form of a frequency range calculated based on the results of bench tests. A critical approach to the problem of preliminary tests of fuel assembly layouts at various stands in terms of the sufficiency of information and its validity is presented. For the convenience of visualization and compression of information, a new representation of the cascade of spectra is introduced in the form of contour graphs, which makes it possible to identify common patterns on a large amount of data as efficiently as possible. The necessity of further research on neutron noise issues at existing nuclear power plants is argued in connection with the introduction of a new fuel assembly design (TVS-5), which has significant differences.

It is necessary to create a reserve of the maximum service life of fuel and structural materials to increase the service life of fuel rods in a nuclear reactor. This paper considers various methods of reducing the radial unevenness of fuel element burnup by redistributing fissionable nuclei (profiling) using the example of the unit cell of the VVER-1200 reactor in the infinite breeding medium. The fuel pellet is divided into a different number of concentric layers to be profiled, the enrichment of the layers varis while maintaining the total number of fissile nuclei in the fuel pellet at the beginning of the fuel campaign. In the Serpent 2 PC, neutron physics calculations of the corresponding models are performed, after that the characteristics obtained for them are compared: the infinite multiplication factor, the average rate of reactivity loss, the proportion of delayed neutrons at the beginning of the campaign, radial burnup profile and energy release distributions (at different time points), and changes in reactivity effects after profiling. The result of this work is a selected optimal method to reduce burnup on the fuel pellet periphery by increasing enrichment in the central part of the fuel pellet and, as a result, a more uniform burnup profile in the whole of the tablet. The research shows that there is no change in the neutron-physical characteristics as a result of the transformations carried out. A possible problem when using this profiling method may be an increase in the peripheral layer temperature as a result of a significant increase in energy release in it during the fuel campaign.

The article presents the results of the analysis of project activities in the field of nuclear energy for Russia, China and India. The purpose of the work is to compare the experience of countries in the development and implementation of national projects in the field of nuclear energy. A brief overview of the development of the countries' project activities is presented, the role of the state is emphasized, the leading national projects are named, the goals and main indicators of their implementation are noted, promising tasks in the field of nuclear energy are highlighted. The novelty of the study is to compare the experience of countries in the development and implementation of national projects in the field of nuclear energy in key aspects, which allows us to get a systematic understanding of best practices, identify common trends and differences, and formulate recommendations for improving the safety and efficiency of the industry. General policy directions in the field of nuclear energy are proposed, which are based on the experience of Russia, China and India.

Methodology and Methods. The research methodology is based on a systematic review approach, including the collection, selection and analysis of existing publications, regulatory, statistical documentation and reporting on national projects of Russia, China and India in the field of nuclear energy. The research used general scientific methods in the form of theoretical analysis, logical and analytical methods, synthesis, the method of comparison and comparison, and the graphical method. Validation of the conclusions was carried out by comparing materials from different sources and their qualitative processing in order to ensure reproducibility and reliability of the conclusions obtained.

Results. An overview of the development of countries' project activities in the field of nuclear energy at the national level is presented, the role of government agencies is emphasized, leading national projects are named, goals, targets and key activities within their implementation are noted, the fulfillment of certain targets of the Russian national project "New Nuclear and Energy Technologies in the field of nuclear Energy" is presented and an assessment is given implementation of the plans of China and India, the main tasks in the field of nuclear energy of the countries are named, The experience of countries in the development and implementation of national projects in the field of nuclear energy in key aspects is compared, features, common features and differences in the approaches of countries to project activities are highlighted, general directions of policy in the field of nuclear energy are proposed, which are based on the experience of Russia, China and India and can be useful for the formation of a state strategy.

Discussion. The results of the study made it possible to identify and compare the specifics of project activities in the nuclear energy sector in the Russian Federation, the People's Republic of China and the Republic of India, and to develop common policies in the field of nuclear energy based on the experience of the countries. Nevertheless, constant updating of the information provided is required, due to the active development of nuclear energy not only in these countries, but throughout the world. Issues of international cooperation aimed at improving safety, reducing risks and increasing confidence in nuclear energy at the global level are also of interest

Occupational safety at uranium mining enterprises remains one of the key components of sustainable industrial development. In conditions of high risks associated with the operation of uranium deposits using the in-situ leaching method, a systematic approach to accident prevention and the formation of a safety culture becomes particularly important. The objective of this study is to analyze occupational injuries at JSC «NAC Kazatomprom» for the period 2019–2024, with an assessment of the effectiveness of applied occupational safety tools, including the implementation of the Vision Zero concept, behavioral audits, the use of digital monitoring solutions, and active personnel training. The methodological basis consisted of integrated annual reports, LTIFR (Lost Time Injury Frequency Rate) indicators, quantitative analysis of accidents and their trends, as well as qualitative assessment of the corporate safety culture at the enterprises. The results of the analysis indicate a pronounced positive trend: while in 2019 there were 8 accidents and the LTIFR was 0, 24, by 2024 these indicators had decreased to 3 accidents and an LTIFR of 0, 09, respectively. The most critical year was 2021 (9 accidents, LTIFR – 0, 55), after which a steady improvement has been observed since 2022. The systemic measures implemented by the company have reduced the injury frequency by more than 2,5 times. The obtained results demonstrate the success of JSC «NAC Kazatomprom»’s strategic approach to occupational safety and confirm the compliance of implemented practices with international standards. The company not only reduces operational risks but also develops a mature safety culture by engaging employees in risk management. The experience of JSC «NAC Kazatomprom» can be recommended for replication at other enterprises in the industry. In the future, it is advisable to expand digital monitoring, involve personnel in safety initiatives, and further consolidate the principles of Vision Zero in corporate policy.