This paper analyzes the methods and technologies for assessing the method of formation, composition, characteristics and features of corium, which is a mixture of nuclear and structural materials of the nuclear reactor core, formed as a result of an accident accompanied by partial or complete core melting. The study is based on data from the study of corium formed as a result of the accident at the Fukushima Daiichi nuclear power plant, which are in the public domain and are the result of the work of many scientific organizations around the world. Corium research is one of the main issues in the framework of improving nuclear safety in the future and is one of the objectives of the successful procedure for eliminating the consequences of the accident at the Fukushima Daiichi nuclear power plant. Without a detailed analysis of the neutronic, materials science, gravimetric and other characteristics of the corium, as well as the creation of a complex model of the corium that combines these data, it is impossible to organize an efficient and safe process for removing nuclear materials from the damaged units of the Fukushima Daiichi nuclear power plant. The objective of this work is to combine the existing research results into a data set that allows modeling of the corium using neutronic calculation codes and includes such data as the size, density and morphology of corium samples and their approximate nuclide composition. Such modeling allows not only to perform tasks related to increasing the level of safety in the implementation of the procedure for eliminating the consequences of the accident at the Fukushima Daiichi nuclear power plant, but also to serve as an international benchmark for modeling a mixture containing nuclear materials.

The paper considers geographical distribution of the countries embarking on the implementation of the first projects for the construction of a large-capacity NPP. The risks affecting the construction of nuclear power plants are presented, the analysis of possible consequences is carried out, in particular, an increase in the cost of building a nuclear power plant and an increase in the duration of its construction in novice countries that are starting to implement nuclear power plant construction projects for the first time, arising as a result of the realized risk. The measures resorted to by the novice countries for the successful implementation of the project and mitigation of risks are considered. The necessity of maintenance of NPP construction and timely preparation for its operation is considered, as well as the analysis of the approaches of the Russian operating organization to the provision of such services at the stage of NPP construction abroad is carried out, the weak competitiveness of the “architect-engineer” approach is discussed, the preference is the “technical customer” and “owner\\s engineer” approaches is provided.

The paper describes perspectives of development and manufacturing of full-scale simulator for training in methods of diagnostics of electric drive equipment used at NPPs. An approximate composition of technical means included in the simulator is given and its technical characteristics are substantiated. The training simulator of diagnostics must include an experimental stand which allows to simulate real operating conditions as well as possible defects of electric drive equipment of NPP, and also an instrumentation park and methodological support used at NPP for diagnostics. Implementation of training in methods and techniques of technical diagnostics with their practical development on the diagnostics simulator will increase the quality of diagnostic support of NPP electric drive equipment operation.

The appearance of free, weakly fixed and foreign objects in the main circulation circuit is not ruled out in reactor plants with a pressurized water power reactor. These objects, moving in the coolant flow, can collide with the inner walls of the main circulation circuit, which can lead to equipment damage. Early detection of these objects will minimize damage and improve the safety of NPP operation. The reactor plant is equipped with a system for detecting loose/weakly fixed objects for this purpose. The main problem is a large number of false alarms arising from the registration of noise from the normal operation of the NPP. The paper considers the application of clustering algorithms to signals of the system for detecting loose/weakly fixed objects, which can significantly reduce the number of false alarms as it has been established that signals from the operation of standard equipment are highly repeatable. Then, having “trained” the system on a certain archive of data characterizing the regular functioning of the NPP, we can state that if the newly received signal falls into one of the clusters, then it reflects the normal functioning of the NPP, while the signals do not that fell into any of the clusters may be the result of the appearance of a loose / loosely fixed object, and this situation requires an immediate response from the personnel operating the NPP. This approach makes it possible to reduce the amount of the system for detecting loose/weakly fixed objects output information significantly, reduce the load on the operating personnel, improve the quality of decisions made and, accordingly, increase the safety of operation of the reactor plant as a whole.

The paper describes a model that confirms the reliability of the diagnostic methodology for the drives of the control and protection system (CPS) of the power units. The model simulates the operation of the diagnostic object which generates signals that are recorded, stored and processed by the Diagnostic System of the CPS drives. This system was developed by MEPhI as a pilot sample designed to diagnose the drive of the ARC of the fourth block of the Novovoronezh NPP and the drive of the LSD of the fifth block of the Novovoronezh NPP. The main requirement for the system is the ability to identify the most common defects in the drives of the ARC and LSD. The system has versatility, mobility, compactness and ease of use, and its technical and economic indicators are higher than the patented objects of industrial property, which indicates the prospects of its use for monitoring the technical condition of the electric drives of CPS in order to improve the safety of NPP. A methodology is developed which establishes the requirements for the content and organization of the procedure for diagnosing CPS drives using a comprehensive information system for monitoring the technical condition and resource characteristics of CPS drives of power units of the reactor WWER-440. This technique applies to the drives of CPS of the ARK and LSD type, which are in operation at nuclear power plants and is intended for specialists who use diagnostic system of CPS for their intended purpose. Validation of the methodology underlying the operation of the system is carried out by processing signals simulating the operation of drives in conditions of the most common defects. The article provides examples of simulated signals containing signs of defects provided by the methodology. The introduction of a validated system and methodology will simplify the task of collecting, analyzing, and comparing data on drives during operation at nuclear power plants, and will also improve the qualifications of personnel, which should have a positive impact on increasing the reliability and resource of equipment.

Researches are done to improve parameters of nuclear reactors and reduce the cost of generated electricity directed towards determining of the most rational fuel usage. Different methods use different mathematical and physical models that results in some differences in received data. One of the methods is profiling of Nuclear Energy Reactors. In this paper the theory that is used in modeling and tallies in Serpent 2 is given, the methods of axial profiling of reactors are shown, comparison of received data and justification of their validity on intermediate state of the research are examined.

The paper provides an overview of career guidance cooperation possibilities between the stakeholders of the educational process and nuclear industry specialists in order to deepen the integration of the school, the technical university and production. A model of collaboration of the main stakeholders to build an effective system of social partnership in the field of vocational education and improve the quality of graduate training for the nuclear industry is proposed.

The paper considers a new approach to the formation of development models of cities of nuclear industry enterprises which is defined as infrastructural-service oriented assuming not only providing residents with modern infrastructure, but also with advanced services, putting the most effective satisfaction of human needs and demands in the city at the forefront. The paper analyzes the impact that universities have on the economy, the level of human capital and innovation potential of the territory of the region in connection with the expansion of university functions and the change in the vector of the functional model of the university - from a universal scientific and educational to an expert-technological one. In recent years, in response to the current challenges in our country, the functions of universities have been transformed, with the main functions (educational and research) emphasizing the function of serving the regional community, in the implementation of which the university acts as a driver of territory development. The article reveals the directions and forms of activities of Volgodonsk Engineering and Technical Institute as a driver of development of Volgodonsk and Volgodonsk agglomeration as a territory of Rostov NPP location.