NUCLEAR, RADIATION AND ENVIRONMENTAL SAFETY
The MTIR-SCP reactor is a research reactor with a light-water coolant having a fast neutron spectrum in nominal operation. None of the existing or projected reactors has a set of these features, therefore, special attention should be paid to the choice of the design of control rods and their location. The article considers various designs of control rods characteristic of the VVER-SCP power reactor currently under development, as well as existing research reactors with a liquid metal coolant having a fast neutron spectrum, taking into account the features of the MTIR-SCP: a seven-element control rod assembly design, as well as a ring-type absorbing element. Efficiency calculations are carried out for each of the structures under consideration and it was determined that the design of a control rod with an annular type of absorbing element has the highest specific efficiency. This design is chosen as the main one for the MTIR- SCP reactor. Criteria are proposed and optimization of the placement of control rods in the reactor core is carried out in order to reduce the uncertainty of obtaining neutron-physical characteristics in the central autonomous loop channel and increase the flow density in it. When optimizing the placement of control rods in the research reactor, their influence on the main neutron-physical characteristics, and especially on their distribution during operation under nominal conditions, is taken into account. Emergency protection and compensating rods that compensate for temperature and density effects when the reactor reaches the nominal power level have been removed, therefore their effect on the neutron-physical characteristics of the reactor and the loop channel during operation at power is not significant, and the compensating rods are located in the core and are removed as the fuel burns out, therefore their effect on the spatial The distribution of neutron-physical characteristics will be significant. To reduce this effect, burnout compensators and automatic regulators are proposed to be moved outside the core into the reflector. For various reactor conditions, the efficiency of the control and protection system was evaluated. It is shown that in various states, the control rods transfer the reactor to the required level of subcriticality, in accordance with NP-009-17.
The article discusses the technical and economic analysis of a seawater desalination plant, where the power source is a hybrid of solar and nuclear energy, as they are considered the cleanest energy sources compared to fossil fuel power plants. The source of nuclear energy in this study is a small modular reactor (SMR). This plant also uses a hybrid of seawater desalination systems: either a reverse osmosis plant with a multi-effect distillation (RO + MED) unit, or a reverse osmosis plant with a multi-stage flash distillation (RO + MSF) unit. Small modular reactors can be used for other applications besides generating electricity, as they produce high-temperature steam which can be used in many industrial processes such as hydrogen production and seawater desalination. Small modular reactors are also considered to be more cost effective, safer, more flexible and have a greater number of applications compared to high power reactors. The analysis is based on calculating the cost of producing of one cubic meter of fresh water using this hybrid desalination plant and comparing the results with those of desalination plant integrated with a power plant that uses exclusively nuclear energy as a source of thermal and electrical power, which uses the VVER-1200 reactor. Also, this study studies the impact of the degree of hybridization, that is, the ratio of power used from solar energy to power used from nuclear energy, on the cost of desalination of one cubic meter of water, as well as on the quality of the desalinated water.
This work is devoted to the problem of neutron field formation near elliptical orbits of space objects equipped with nuclear power plants. The high-energy part of the fission spectrum is not affected by the gravitational field. Radiation safety is ensured by the triad fair for a point source: activity-distance-time. The connection between space object orbit parameters and neutron flux density occurs for the thermal (near-thermal) part of the spectrum. The possibility of formation of a stable neutron trace in the volume of a «torus» around the orbit of a space object is considered. The paper presents theoretical and numerical evidence of the validity of the hypothesis put forward. The introduction considers the separation effect of Galileo's relativity principle in the case of rectilinear uniform motion of a point isotropic neutron source on a plane. The occurrence of angular asymmetry of the neutron distribution in a stationary coordinate system when their relative velocity is close to the transport velocity of the source is illustrated. Under these conditions, a significant velocity dispersion of initially monochromatic neutrons is also recorded. This expected fundamental kinematic effect determines the characteristic distribution of neutrons in the gravitational field when the source moves along the Kepler orbit. The solution of the problem is carried out in the velocity space. It is argued that if the distribution of neutrons in the velocity space is such that their velocities are collinear to the orbital velocity of the source, this indicates the existence of a neutron flux near the orbit. The problem is analysed on the example of one revolution of a hypothetical space station by simulation modelling. For this purpose, thermal neutron packets with isotropic angular distribution were generated at eight points of an elliptical orbit. The neutron and source velocity fluxes at the selected points of the orbit were compared in a coordinate system related to the earth. The obtained data made it possible to calculate the densities of neutron velocity fluxes to the front and rear hemispheres relative to the source orbital motion as a function of the polar angle, while the value of the determinant of the correlation matrix – an indicator of collinearity of neutron velocity vectors in the flux - was fixed. The results of the studies confirm the hypothesis put forward about the possibility of formation of a «trace» in the orbit of a thermal neutron source, which determines the need to take it into account as a significant component of radiation risk.
DESIGN, MANUFACTURE AND COMMISSIONING COMMISSIONING OF EQUIPMENT NUCLEAR INDUSTRY FACILITIES
The relevance of this work is determined by the need to predict the operation of sealing assemblies for elements of localizing safety systems (LSSs) of power units with VVER, which include (penetrations, hatches, locks, doors and other elements of hermetic fencing (GF) in operational modes. Operational modes are understood as modes of normal operation, modes of violation of normal operation, as well as emergency situations. During the manufacture and operation of LSS elements, the problem arises of uneven protrusion of a double-row rubber seal from the grooves in the web of the LSS element, which leads to the need to clarify the integral compression force of the seal as a whole for this element. The problem is caused by the imperfection of the manufacturing technology of large canvases for LSS elements (doors, hatches, locks: the perimeter of the seals can reach 10-20 m, the diameter of the canvas 2-6 m) and the need to withstand stringent technological requirements for flatness, parallelism and marginal deviations in linear and angular dimensions. The manufacture of overall structures is complicated by the presence of welded joints, heat treatment, and the complexity of metalworking. Compression force of the PNAE rubber gasket-7-002-86 it is not regulated, therefore, for the reliable design of gasket compression mechanisms, the magnitude of this force was determined. Based on the obtained results of tests of rubber seals for tightness and cyclic loading [7], an assessment of the tightness of the applied rubber seals is performed, calculations of deformations of rubber seals are performed using the FEM software package. Recommendations have been developed to increase the reliability of seal assemblies for elements of localizing safety systems (LSSs) of VVER power units in operational modes and to select the compression value to determine the necessary force to ensure tightness at the beginning of operation and after 5000 opening-closing cycles.
The quality requirements for pipeline fittings for NPPs and oil and gas facilities have become more stringent recently, which is related to ensuring their safe operation life. When manufacturing parts using subtractive machining technologies, special importance is attached to accuracy indicators of linear-angular dimensions and surface shapes. This study examines ways to optimize dimensional turning using the example of a “separator” part on a multifunctional CNC turning and milling center MULTICUT 630/2000S. Operations of designing and optimizing the production of parts are increasingly determined by the results of simulation modelling, virtual models, which, in fact, are an integral part of technological processes. In this work, simulation modelling is performed on simulators with CNC Sinumerik 810/840D/Operate Turn. This procedure is a simplified version of the Weiler-Atherton clipping algorithm as applied to stock removal turning. In addition to the algorithm, additional modules for dynamic corrections of control programs are proposed in order to guarantee the requirements of design documentation for accuracy in the conditions of a dynamic SPID system: machine – fixture – tool – part. The cutting speed, depth of cut and tool feed in turning have the greatest influence on the stock removal process from the technological control parameters. Modules of dynamic corrections of control programmes allow to estimate quite accurately the influence of control factors in turning (cutting speed, depth of cut and feed) on cutting force and machining accuracy.
OPERATION OF FACILITIES NUCLEAR INDUSTRY
The welded joint zone (WJ) No. 111 is a welding unit for the "hot" collector of the primary coolant to the DN1200 steam generator nozzle. The experience of operation of steam generators PGV-1000M of NPP power units with VVER-1000 shows that the WJ zone No. 111 is prone to the formation and development of operational defects. According to the results of periodic non-destructive testing of the WJ No. 111 zone performed at the PG of various power units of the VVER-1000 NPP, cases of detection of extended planar-type discontinuities, including through ones, were repeatedly recorded. Thus, this zone is one of the most critical zones of the reactor plant (RU) with VVER -1000. The root cause of the formation and development of operational defects has not yet been identified. Solving the problem of cracking of WJ No. 111 steam generators of nuclear power plants with VVER-1000 is one of the priority areas for improving the safety of operation of the power unit during the over-design service life. This problem is determined by a complex combination of temperature conditions, mechanical and corrosive effects, is relevant and has not yet been definitively solved. Therefore, it is very important to ensure the collection of reliable data on the actual stress-strain state of the WJ No. 111 zone in various operating modes (pressure loading of steam generators, heating/cooling of the power unit, hydraulic testing of the 1st and 2nd circuits). The article reveals the approaches and stages of creating and applying a strain gauge installation to ensure metrological suitability in the conditions of a campaign fuel company at an NPP power unit by using an adequate physical model to obtain additive and multiplicative correction coefficients.
This article proposes the multipoint kinetics model consisting with different number of point kinetics model (two points, four points, six points, eight points, ten points) in the axial direction for the
VVER-1200 nuclear reactor. Each node is coupled with others through the coupling coefficients determined from the diffusion approach. For more precise description of the dynamical modes of the reactor operation, the proposed model integrates the power reactivity feedback derived from temperature reactivity coefficients and Mann’s thermal hydraulic model which assumes one fuel node adjacent to two coolant nodes. On the model with four axial points, additionally was tested the influence of the different number of delayed neutrons groups on the accuracy results and model running time during the load-following mode of operation. Moreover, the novel model of the control rods is introduced, utilizing a combination of sign functions to sequentially influence all nodes during insertion or withdrawal. The computational results show that the accuracy of the proposed model is satisfactory, and general assumptions about transients align with their physical definitions. This research contributes to the advancement of the point-like nuclear reactor modeling for improvement of the automatic power controller synthesis.
SAFETY CULTURE AND SOCIO-ECONOMIC ASPECTS DEVELOPMENT OF PLACEMENT TERRITORIES NUCLEAR INDUSTRY FACILITIES
The article considers the problem of implementing the process of digitalization of the energy industry, using the example of the Rosseti group of companies, a partner of the state corporation Rosatom in the field of IT development, from the point of view of staffing in the current state of the labour market. The purpose of the research work is to develop relevant mechanisms, search for modern personnel management tools in the context of digital transformation of the electric grid complex of the Russian Federation. The scientific novelty of the research is reduced to the following provisions: the main directions of digitalization of an electric grid company are systematized, on the basis of which the organizational and economic mechanism of the process of digital transformation of an electric grid company is modelled; a classification of modern tools of the business process of personnel management of an electric grid company is proposed. Methodology and methods. To study trends in the digitalization process of electric grid companies, general scientific methods are used (theoretical analysis of scientific works, empirical, logical, classification and modelling methods). A review of publications is carried out, which made it possible to determine the subject area of the research work. Results. The main processes within the electric grid company that will be transformed in the process of digitalization are considered, using the example of the Rosseti Group of Companies. Taking into account the considered areas of digitalization of activities, an organizational and economic mechanism of the digitalization process of an electric grid company has been formulated, which is distinguished by the rationale for the author’s definition of digitalization on the scale of the energy industry. The role of high-quality staffing in the implementation of digital processes and activities of electric grid companies is determined and specific requirements for applicant’s characteristic of the energy industry are identified. The structure of the human resource management business process is considered, digital tools are selected for each subprocess that will help improve staffing levels and the efficiency of using labour resources of the electric grid company. Discussion. An effective personnel policy aimed at maximizing the company's staffing with qualified personnel is one of the key solutions in increasing the reliability and sustainability of the energy industry during the period of digitalization. Standard tools in the field of personnel management may not work in the context of both a demographic personnel shortage and the current migration of labour resources to the defence and military industries. Constant adaptation of the used methods and practices of personnel management is required, taking into account the digitalization of this business process and the challenges that the energy industry of the Russian Federation currently faces.
The paper considers the available artificial intelligence platforms used in the preparation of technical English assignments and the ways of motivation to learn a foreign language as the object of research. The processes of providing motivation for learning are chosen as the subject area. The objective of the research is to show the possibilities and spheres of AI use in foreign language teaching on the basis of analysing the information presented in the public domain about the existing ways of artificial intelligence application in foreign language teaching, as well as the conducted survey of nuclear engineering students. The methods used in the paper were theoretical analysis of scientific literature, analysis of periodicals, analysis of the practical use of AI in the work of teachers of the Department of Foreign Languages, as well as the data of the survey conducted among the students of technical specialities of VETI MEPhI. The main result of the research is the conclusion that the use of AI allows to diversify didactic material, provide motivation of students to master technical English and understand technological processes through the use of video content.
This article considers the process of transformation of the Russian Federation nuclear law into an independent public complex branch of law and its important role in improving global nuclear safety. Since it is well known that the criteria of distinguishing branches of law are usually the subject and method of legal regulation as well as the existence of their own codification, the authors are confident of such a need. The results of the analysis of the state corporation Rosatom activities serve as the basis for the proposed theses and only confirm this confidence. The main idea of the article is to assert the need for changes in the Russian legal system structure in order to increase the effectiveness of regulation in the field of nuclear safety. The paper examines the evolution of nuclear law in Russia, identifies the basic principles and norms of this area of law as well as the need to make changes to adapt to modern challenges and threats. Supporting its position by analyzing the current state of the Russian nuclear industry and world standards in the field of nuclear safety, the article suggests practical steps to strengthen legal regulation to ensure safety in the nuclear field. Special attention is paid to the importance of strengthening international nuclear safety through the modernization of the national nuclear legal system, its compliance with international norms and standards. The article discusses current issues, including the development of nuclear doctrine, control of nuclear materials, responsibility for violation of international nuclear obligations and other aspects affecting global nuclear security. The study is an important contribution to understanding the problems of nuclear law in the context of global safety, and also substantiates the need for independent development of this branch of law to ensure stability and security on the world stage. The authors of the article offer specific recommendations for improving legislation and practice in the field of nuclear law in order to strengthen global nuclear safety
ISSN 2499-9733 (Online)