The ammunition placement in a small area creates the group explosion danger as a result of destructive effects. It is impossible to ensure the group explosive safety of ammunition, by increased distance between them, due to the limited volume in which they are placed. This can be achieved by using protective screens against the high-speed strikers impact. Another direction is the search for optimal ammunition placement schemes in storage that minimize the number of fragments falling into ammunition. The neutrons external background influence during the group storage of nuclear ammunition is also considered.

The paper describes ballistic test site equipment used for studying the physical and mechanical properties of materials exposed to intense dynamic loads. To study the properties of shock-compressed substances, explosive shock wave generators based on powerful condensed explosives are used. The methods of dispersal of the used strikers in different throwing modes with different types of guns are briefly described. The methodological development in cannon experiments on light-gas guns is given, in which the conditions of safe acceleration of the strikers in the barrels of the guns and the loading parameters of the latter which provide the required collision speeds of the striker and the target are confirmed. Numerical and experimental results of testing the selected throwing modes are presented.

The paper discusses the issues of international cooperation on environmental issues in Nigeria: the role of international agreements in the field of environmental ecology; basic principles of international cooperation in the field of environmental protection; environmental education in Nigeria; principles of environmental project management; and a number of measures to reduce atmospheric pollution. The issues of coordination both between the state and between international organizations dealing with similar problems, as well as issues of mutually beneficial cooperation in the field of environmental ecology are considered in the research paper. The issues under consideration acquire particular relevance in connection with the discussion of the possibility of nuclear power plant building in Nigeria.

Increased demands are placed on the reliability and strength of structures used in the installation of equipment for nuclear power plants. At the same time, an excessive safety margin of the equipment used leads to an increase in its dimensions, weight and a significant rise in cost. The issue of reducing the metal consumption of structures while maintaining the required performance criteria for this equipment is very relevant. The paper presents a model for optimizing the design of a three-beam traverse with a carrying capacity of 100 tons for reactor cavity reinforced concrete block installation. A verification calculation is carried out and recommendations on the optimization of design parameters are proposed on its basis.

The article deals with the one-group approximation to the problem of parametric identification of the distribution of isotropic sources, providing the required configuration of the neutron field in vacuum.

The compensation for the excess reactivity in the pressurized water reactors WWER is realized with high neutron absorber materials. The traditional excess reactivity regulation methods lead to unfeasible neutron utilization and reduce the breeding coefficient and fuel burnup. In the current work, the change of moderator-to-fuel ratio is investigated as one of the spectral regulation methods for excess reactivity control and its effect on the fuel burnup. Cylindrical Zirconium rods (Zr rods) are used to fulfill the moderator-to-fuel ratio change. The Zr rods are placed between fuel rods in WWER-1000 fuel assembly. The current work calculations are performed for the thorium fuel cycle (Th-U233). The change of the Zr rods diameter leads to the variation in moderator-to-fuel ratio. A comparison between the Zr rods as a reactivity regulator in WWER-1000 fuel assembly for both fuel cycles UO₂ and Th-U233. The concentration of the fertile and fissile fuel components for both fuel cycles has been analyzed. The fissile isotopes accumulation coefficient can reach 0.75 with the decrease of the moderator-to-fuel ratio in the Th-U233 fuel cycle. The primary safety parameters such as the Control rods worth, Doppler Effect reactivity coefficient, and Moderator Temperature reactivity Coefficient have been studied at different moderator-to-fuel ratio values. The safety parameters in the Th-U233 fuel cycle have higher values more than the UO₂ fuel cycle with the insertion of Zr rods. From the comparison between the Zr rods effect in both fuel cycles, it is clearly shown that Zr rods in the UO₂ fuel cycle have a more influential role in regulating the WWER-1000 core reactivity compared with its effect in the Th-U233 fuel cycle.

The research work considers and analyzes the problem of control valve failure in case of shaft-gear break during normal operation. In order to identify typical deviations and causes of failure of the electrically driven valves, the amplitude-frequency spectra of the current signal taken at one or more phases of the electric motor were analyzed. The method of spectral diagnostics adopted for analysis allows detecting hidden defects of reinforcement not detected in other types of analysis. In order to justify the study, spectral analysis is carried out on control valves installed in the main condensate and feedwater systems of power units WWER-1000 and WWER-1200. As a result of the study, the following relationships were established increase of amplitude speed of electric motor (EM) to -30 dB is a fact of EM operation at increased load, which will lead to wear of thrust-radial bearings; appearance of baseband frequencies in the region of 50 Hz frequency indicates that there are deviations in setting of electric drive torque limiters. The detected defects, in the future, will lead to the failure of the gear shaft and the shutdown of the power unit. The results of the performed work are used to supplement the existing catalog of defects of pipeline valves developed by RI NPE VETI NRNU MEPhI.

The Rostov nuclear power plant is the largest energy center in the South of Russia. Electricity from the nuclear power plant is transmitted to nodal substations across the territory of the Southern region, the climatic conditions of which contribute to the formation of ice deposits on power lines, this determines the urgency of the problem of ice melting. Existing systems for early detection of ice and melting it on wires of 110-500 kV overhead lines allow preventing wire breakage and destruction of supports. In modern methods ice melting is performed with alternating and direct current using special transformers and rectifiers with a melting voltage of 10 kV and a melting current of up to 3600 A, currents and voltages to prevent overheating of contacts in melting circuits and compliance with melting parameters. In circuits using direct current, there is no reliable method for controlling its magnitude. The paper considers the possibility of using a fiber-optic current sensor with a measurement range from 1 to 3600 A.

The article actualizes the political, legal, socio-economic and socio-cultural aspects of safety culture in the Russian Federation. The article offers a general analysis of the current regulatory framework that defines the conceptual foundations for the formation and development of a culture of life safety, a culture of economic security and environmental culture in the Russian Federation.

The paper considers the concept and fundamental principles of safety culture which along with the high professionalism of service personnel in Russia and abroad as well as the reliable operation of all production and technical systems, are necessary conditions for nuclear and radiation safety of energy enterprises. Taking into account the influence of national culture on safety culture, training in the effective use of tools for preventing personnel errors along with the high quality of education of foreign students will contribute to the formation of a principled position in the field of safety and efficiency of functioning of nuclear facilities.