No 1 (2022)
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THE PROBLEMS OF NUCLEAR, RADIATION AND ECOLOGICAL SAFETY
Methods of Assessing Radioactive Contamination of Underlying Surface Using Unmanned Dosimeter System
6-23 221
Abstract
The paper considers methods of estimating radioactive contamination of the underlying surface, based on two scenarios. In the first one the analysis of contamination is performed within the framework of a geophysical model of the surface layer of the atmosphere, while the transport of radioactive admixtures, which causes contamination of the underlying surface, is calculated within the turbulent diffusion model. The second scenario consists of an analysis of the radioactive contamination of the underlying surface, which has a random nature due to technogenic causes, and its implementation is carried out by means of an unmanned dosimetric complex (UDC). The latter allows to considerably reduce direct human involvement in radiation reconnaissance of the territory.The work draws attention to the program of drone flight (altitude, route, etc.), composition of the dosimetric complex, mathematical support of the unmanned dosimetric complex, mathematical models of atmospheric meteorological parameters estimation underlying the model of surface layer and radioactive admixture distribution in the atmosphere.
24-30 147
Abstract
The article studies the emergency development accompanied by an explosive item explosion (burning) which contained in nuclear weapon and by a scattering nuclear fissile material into the environment. The impurity propagation simulation in atmosphere at the inactive explosion case was executed.
RESEARCH, DESIGN, CONSTRUCTION AND INSTALLATION OF NUCLEAR FACILITIES MANUFACTURING EQUIPMENT
31-40 217
Abstract
The article is devoted to the project of the modernized television mast of the refueling machine MPS-V-428 of the Tianwan NPP first unit. The goal of the modernization is to reduce the economic costs at the NPP during the scheduled preventive maintenance due to the imperfection of the existing design of the refueling machine TV-mast due to which the unit downtime is overestimated.
41-45 130
Abstract
The article considers the feasibility of using powder materials for the manufacture of a number of products used in the nuclear power industry. Taking into account high requirements to the products operated in nuclear industry, the questions of studying the properties of materials obtained by powder metallurgy methods and its behaviour in different conditions are topical. Results of investigations on influence of temperature on plastic properties of powder material during hot upsetting of porous cylindrical samples are given. It is established that at temperature of recrystallization (ferrite to austenite transition) plastic properties of porous material decrease.
OPERATION OF FACILITIES NUCLEAR INDUSTRY
A. I. Al-Shamayleh,
D. A. Solovyov,
A. A. Semenov,
N. V. Shchukin,
A. L. Lobarev,
D. A. Plotnikov,
V. S. Potapov
46-59 243
Abstract
Activation of the emergency protection entails the entering of boric acid solution into the reactor core to the parking value, then the control rods are raised, after which it is possible to obtain permission to start the reactor. The first stage of reaching the minimum controlled level (MCL) of power is feeding with pure condensate to the start-up interval at a high injection rate, the second is mixing the 1st circuit and then entering the pure condensate but at a low speed. At the same time, the technical regulations for safe operation indicate that the flow rate of pure condensate in the start-up interval should not exceed the flow rate of pure condensate to compensate for xenon poisoning by more than 10 t / h, and the input rate of positive reactivity should not exceed 0.02 βeff/min. At the same time, it is not entirely clear how to estimate the flow rate of pure condensate in the start-up interval, since there is no equipment on the power unit that measures the magnitude of xenon poisoning and the rate of reactivity input. This article will answer the question of what is the permissible flow rate of pure condensate the operator can use in the start-up interval in the presence of xenon processes.
60-66 143
Abstract
The scope of the research work is a complex of problems related to the processes of collecting and storing the results of thermographic control (TCE) used at nuclear power plants (AS) to assess the technical condition of equipment that directly affects safety. As a solution to eliminate existing problems, a comprehensive automated system for storing and analyzing the results of thermographic control of NPP equipment (CAS TVK) is being developed at the Research Institute of AEM VETI of the MEPhI Research Institute .
SAFETY CULTURE, SOCIO AND LEGAL ASPECTS OF TERRITORIAL DEVELOPMENT OF NUCLEAR FACILITIES LOCATION
67-74 159
Abstract
The article justifies the importance of applying the competency-based approach for personnel training in accordance with the current demands of the real economy sector. An example of the development and implementation of the system approach by enterprises of the State Atomic Energy Corporation "Rosatom" to form the competence "Technological systems of power facilities" is given. The importance of this competence of ensuring the growth of productivity, efficiency and safety of nuclear power plants (NPPs) operation was noted. Involvement of educational organizations, enterprises of nuclear industry and other interested parties allows to approach comprehensively to the solution of an actual problem of development of in-demand skills and abilities of future specialists. The essence features of the competence are considered, as well as the plan and measures for its popularization both within enterprises and educational organizations in the territory of NPP presence.
75-85 160
Abstract
The paper considers the sectoral system of professional qualifications assessment in the field of nuclear energy, its structural components, and reveals the main tasks and activities for its improvement and development. The relevance of independent assessment of qualifications of future engineering personnel specialized in nuclear power industry at the stage of completion of higher education is disclosed.
ISSN 2305-414X (Print)
ISSN 2499-9733 (Online)
ISSN 2499-9733 (Online)