The aim of the article is the computational validation of compatibility of the developed transport packing set (TPS) to normative safety requirements in the conditions of land transportation of used fuel assemblies (UFA). The safety of UFA transportation should be confirmed by TPS tightness preservation at emergency falling from height of 9 m on a horizontal surface and from height of 1 m on the pin with circular section. The mentioned tests are simulated by numerical calculations in the finite-element analysis program which shows that suggested TPS construction meets normative requirements.

The issue of detecting and preventing attacks on applications has been and remains one of the urgent tasks of information security. Flaws in the program code lead to disruption of the normal operation of the software. Data integrity, availability and confidentiality of the data, interruption of the execution of running processes or even the system as a whole may occur due to design flaws. This paper discusses the mechanism of buffer overflow on a stack as well as existing modern means of detecting or preventing buffer overflows such as ASLR, StackGuard, and a non-executable stack. These security features are chosen as the research target because they are the most common and are built-in security features in Linux. The objective of the work is to analyze the problem of buffer overflow and the incomplete effectiveness of existing commonly used means of preventing and detecting this type of attack as well as a description of an alternative way to solve the problem of buffer overflow. As part of the work for each of the widespread means of protection considered a way to circumvent it. The result of this work was the conclusion that the existing security tools have significant drawbacks and therefore requires the development of an additional remedy, the idea of which is proposed at the end of the article.

The work studied core elements of the hollow cross-section created by a promising technology that does not require large energy costs. The change in the critical forces depending on its transverse dimensions is revealed based on the numerical analysis of the hollow element stability under central compression. It is found that the material of the rod element influences the critical stresses. The paper shows that the calculations of the hollow element stability are coherent with the experimental data on models.

The article deals with the influence of surface tension forces in one-sided arc welding of butt joints on weight. It shows analytically the possibility of holding the liquid metal of the weld pool when the thickness of the welded parts is from 10mm. and above.

The paper deals with the problem of increasing the accuracy of the processing of nuclear engineering products. The calculations show that the main (significant) component of the processing error is the dynamic error, that is, in the conditions of the system. Experimental studies is confirmed this conclusion and shows that the main factor is the temperature deformation of the product during processing. The influence of this factor can be minimized by changing the parameters of the processing modes so the experimental dependencies can be used.

The problem of the failure of steam generator collectors is actualized and its causes are revealed, one of which is the use of irrational technological processes of fixing heat exchanging pipes to tube sheets. The results of the study of the hydraulic rolling technology influence on the state of press joints are given which allowed to analyze the existing technology and determine reliable criteria to assess the quality of the pipe-tube-board connections.

The paper proposes methodology and design of the stand which allowed to conduct thermal tests of longitudinally-finned tubes of separators-superheaters for nuclear power plants with water-water power reactors of high efficiency. According to the results of tests of longitudinally ribbed pipes with the number of U-shaped ribs equal to six and eight, a comparative analysis is conducted. It is shown that the increase in heat transfer surface exceeds the decrease in heat transfer coefficient for such structures.

The paper considers the possibilities of applying logistics in the design and implementation of the decommissioning process of nuclear power plant units to improve the efficiency and safety of design and practical solutions for managing material and information flows.

The paper describes the method and software developed by the authors for automating operational calculations of reactivity changes of the WWER-1000 reactor. The main calculation dependencies, screen forms and test results are given. Rising of the calculation accuracy is shown. The development path of the developed software as an element of the digital twin of the WWER 1000 nuclear reactor is proposed. 

Development of measuring technologies creates the corresponding problems when carrying out metrological tests. In particular, the need for taking note of the used interface on properties of errors of results of measurements appears. Emergence of errors of dating is a consequence of more and more wide circulation of multipurpose measuring means generates requirement of development of the corresponding procedures of the metrological analysis, including metrological tests. Therefore, the problem of improvement of metrological tests of measuring systems in general and their subsystems is relevant. The scientific novelty consists in development of an algorithm of tests and a conclusion of the estimated ratios connected with definition of probabilistic characteristics of the corresponding errors. The practical importance consists in development of the block diagram of a test experiment. Innovative value consists in a possibility of synthesis of test techniques for certification of the measuring subsystems and measuring systems in general considering dating errors within shift errors.

The paper considers the methods of monitoring the geometric parameters of the berth-calibrator of fuel assemblies (FA) used in the WWER-1000 reactor to form a controlled nuclear reaction and to obtain thermal energy. Variants of technology monitoring are implemented under the assumption of fuel assemblies for their installation in the reactor at the stage of the nuclear power plant installation and its operation.

The paper analyzes the impact of spent nuclear fuel of WWER-1000 reactors of various operating conditions, such as the concentration of boric acid dissolved in water, the temperature of the fuel and others on the isotopic composition. Another factor of influence is the technical characteristics implemented in the production of fuel assemblies, in particular the mass of fuel, its enrichment and other mass-dimensional characteristics of fuel assemblies (FA). Calculations are carried out on models of fuel assemblies of the WWER-1000 reactor. The basis was taken of a typical fuel assembly of the Russian suppliers of fuel elements and fuel assembly of the Westinghouse American company.

This paper is devoted to the study of the state and the problems of radioactive waste management (RW). Particular attention is paid to the final isolation of radioactive waste by the example of a near-surface disposal site for radioactive waste from the Novouralskoye department of the Seversky branch of the National Operator for Radioactive Waste Management (NO RW) in Novouralsk, Sverdlovsk Region. The paper carries out a study of the safety and environmental technologies used in the enterprise. The main research methods are the study of expert opinions, public opinion polls, in particular, students of higher and secondary vocational education of the Novouralsk Technological Institute of the National Research Nuclear University MEPhI as well as their comparative analysis. Recommendations for improving the culture of the population in the use of nuclear technologies are proposed.

The article reveals the relevance of developing a safety culture of schoolchildren in the system of organizing advanced training of engineering personnel for nuclear energy at the stage of innovative development of the industry; considers the possibility of professional orientation to the specialty areas of training, specialized for nuclear energy in the field of developing a safety culture of schoolchildren.