Персона:
Загребаев, Андрей Маркоянович

Организационные подразделения

Организационная единица

Институт интеллектуальных кибернетических систем

Цель ИИКС и стратегия развития - это подготовка кадров, способных противостоять современным угрозам и вызовам, обладающих знаниями и компетенциями в области кибернетики, информационной и финансовой безопасности для решения задач разработки базового программного обеспечения, повышения защищенности критически важных информационных систем и противодействия отмыванию денег, полученных преступным путем, и финансированию терроризма.

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Загребаев

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Андрей Маркоянович

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Теперь показываю 1 - 10 из 10

Только метаданные
Creation and visualization of archives of operational RBMKs parameters and VVER reactors
(2020) Zagrebayev, A. M.; Leveev, I. Y.; Pilyugin, V. V.; Ten, S.; Загребаев, Андрей Маркоянович; Пилюгин, Виктор Васильевич
© 2020 National Research Nuclear University. All rights reserved.This article describes the mathematical apparatus for express analysis of the operational parameters' archive. The developed algorithms, based on the methods of reducing the dimension of the space of variables and the "Chernoff Faces" method, allow visualizing the dynamics of changes in generalized limiting parameters, as well as visually determining the approximation or intersection of the valid parameters values, which in turn can provide scientific and practical use in improving quality of operational personnel work and analysis of situations requiring additional attention and more detailed analysis.
Только метаданные
Creation And Visualization Of An Operational Parameters Archive
(2021) Zagrebayev, A. M.; Ten, S. V.; Загребаев, Андрей Маркоянович
© 2021, Eurasian Journal of Mathematical and Computer Applications. All Rights Reserved.The developed methodologies allows visualizing the behavior of limiting parameters over time and identifying patterns in the dynamics of changes in the parameters of a well as determining if any of the parameters intersects the safe operation settings. The relevance of the work is due to the importance of high-quality processing of data from the nuclear reactor archive using modern effective methodologies. to the analysis of archived data can improve the efficiency of power plant operators.
Только метаданные
Software Package for Three-Dimensional Visualization of the Behavior of Neutron Fields and Archived Parameters During the Operation of the RBMK-1000 Reactor
(2022) Bukalin, A. O.; Zagrebayev, A. M.; Pilyugin, V. V.; Букалин, Алексей Олегович; Загребаев, Андрей Маркоянович; Пилюгин, Виктор Васильевич
© 2022 National Research Nuclear University. All rights reserved.This paper describes the calculation algorithm, software package and visualization of the three-dimensional neutron field deformation according to the archive of the RBMK (high-power pressure-tube reactor) reactor operational parameters. The determination of the field deformation is based on finding "natural" functions for approximating the readings of in-reactor control discretely located sensors. This paper considers the use of generally accepted harmonic functions and "natural" functions for describing the spatial deformation of the neutron field. It is shown that to describe the deformation of the neutron field, it is sufficient to use only a few "natural" functions, in contrast to the use of all harmonic functions from a given set. This, in turn, opens up new possibilities, in particular, for solving the problems of predictive diagnostics of in-reactor control sensors.
Только метаданные
Simplified Mathematical Model and Realization of the Remaining Life of Nuclear Fuel Upon Decommissioning of RBMK-Type Reactor
(2019) Zagrebayev, A. M.; Zaluzhnaya, G.; Naumov, V. I.; Загребаев, Андрей Маркоянович
© 2019, Springer Science+Business Media, LLC, part of Springer Nature. The realization of the residual life of nuclear fuel upon decommissioning of a RBMK type channel reactor is studied. A mathematical model of the energy-production spectrum of FA is presented. Two methods of decommissioning a reactor depending on the method of criticality conservation are compared. The first possible method of conserving the criticality of a reactor upon commissioning is extraction of the FA with high energy production and the second is formation of a two-zone load: fresh FA are placed at the center and spent FA at the periphery. The second method gives a greater advantage in terms of power and remaining energy-production life. The results were obtained in a point model of the dynamics of the FA spectrum in a linear fit to the FA power and multiplication coefficient versus energy production and attest the fundamental possibility of optimizing fuel use and decommissioning of a RBMK reactor.
Только метаданные
Preprocessing and visualization of the VVER reactor operational parameters archive
(2021) Ten, S.; Zagrebayev, A. M.; Pilyugin, V. V.; Загребаев, Андрей Маркоянович; Пилюгин, Виктор Васильевич
© 2021 National Research Nuclear University. All rights reserved.For the most part, the solution of the problem of visualizing any data depends on the structure, size and type of data provided. In this work, the data are archives of RBMK or VVER reactors provided from different control and protection systems of the reactors. Despite the fact that several visualization complexes have already been developed, the visualization task is still relevant due to the necessity to improve the quality of monitoring systems and operational personnel. This paper describes the mathematical apparatus for express analysis of the archive of operational parameters of a VVER nuclear reactor. The developed software makes it possible to carry out express analysis of the VVER reactor archive in terms of plotting altitude or time graphs, as well as using dynamic visualization using the Chernoff faces method, which in turn can provide scientific and practical benefits due to improvement the work quality of operating personnel and conduction analysis of situations that requires additional attention and more detailed analysis. Also, the fundamental concept of this work is the method of scientific visualization, which is widely used in various theoretical and experimental studies. It can be said that the main aim of scientific visualization is to make invisible visible.
Только метаданные
Predictive Diagnostics of Control Sensors in a Nuclear Reactor
(2024) Ten, S. V.; Zagrebayev, A. M.; Загребаев, Андрей Маркоянович
Только метаданные
Optimum Control over the Power of a Load-Following Nuclear Reactor during a Period of Threatened Extreme External Effects
(2024) Evstyukhina, E. V.; Zagrebayev, A. M.; Trifonenkov, A. V.; Загребаев, Андрей Маркоянович; Трифоненков, Андрей Владимирович
Открытый доступ
The analysis of RBMK neutron flux profile distortions using operational data history
(2020) Zagrebayev, A. M.; Trifonenkov, A. V.; Загребаев, Андрей Маркоянович; Трифоненков, Андрей Владимирович
© Published under licence by IOP Publishing Ltd.In this research the operational data history was analysed. The data set given represents RBMK-1000 parameters for one month of the reactor operation. Axial flux sensors data and channel power data taken from database were considered. The transients of axial and radial-azimuthal neutron flux distributions were visualized. For the flux distribution data from 72 core channels with axial flux sensors the axial offset transients were obtained. In the operational data considered xenon-induced power oscillations were revealed. Phase and amplitude transients of the oscillations were calculated. The dynamics of phase and amplitude were visualized over the reactor core cross-sections. The values of quantities were displayed with different color shades. The iodine-135 and xenon-135 concentrations recovery problem solution was considered. Formulas for concentrations recovery were derived. The recovery procedure obtained is based on Cauchy problem solution calculation process. The dependence of accuracy of the recovered transients on the amount of the available operational data was studied. The dependency graph of calculation error on the amount of operational data was plot. The recovery of xenon-135 concentration was carried out based on the operational data history of the power unit where the phenomenon of xenon-induced power oscillations was observed.
Открытый доступ
Mathematical model of the distribution of the coolant flow rate in the group distribution header and its use to determine the flow rate in the RBMK reactor channel
(2020) Zagrebayev, A. M.; Ramazanov, R. N.; Загребаев, Андрей Маркоянович; Рамазанов, Рустем Нурович
© Published under licence by IOP Publishing Ltd.The paper proposes an elementary mathematical model of the distribution of coolant flows through water communications in the group distributing header (GDH) of a power unit with an RBMK reactor. This model used to determine the flow rate in the channel with a "forbidden"flow meter. An equation is given based on the mass balance of the coolant in the allocated volume. The results of the solution are used to construct an algorithm for determining the flow rate of the coolant in the channel. The results of the application of the technique on the measurement data from the power unit are presented. It is shown that the relative discrepancy with the measured value of the flow rate at a constant position of the flow control valve is on the order of several percent.
Только метаданные
Visualization of the process of neutron-physical calculation of a nuclear reactor
(2020) Bukalin, A. O.; Zagrebayev, A. M.; Samanchuk, V. N.; Букалин, Алексей Олегович; Загребаев, Андрей Маркоянович; Саманчук, Владимир Никифорович
© 2020 National Research Nuclear University. All rights reserved.This article describes a computer program for visualization of the process of solving the diffusion equation by the source iteration method. This method is used in the overwhelming majority of software systems for calculation of VVER and RBMK reactors. This program allows you to visually demonstrate the process of obtaining the neutron field micro- and macrostructure (macrofield) in course of the iterative solution of the equation. Visualization of the iterative process allowed us to establish the fact of the rapid appearance of the microstructure of the solution at the first iterations and the slow appearance of the macrofield of the neutron flux density. This fact made it possible to propose a new approach for solving the diffusion equation, namely, to extract the low-frequency component from the initial data of macroscopic interaction cross sections using digital filtering methods; then initially perform the calculation with filtered macroconstants on a coarse grid, and finally on a fine grid. The studies have shown that the calculation of reactor is accelerated several times even on a one-dimensional model, which means that when solving a three-dimensional problem, the solution speed will increase by orders of magnitude. This is important when solving optimization problems and «online» calculating emergency situations.