Персона: Загребаев, Андрей Маркоянович
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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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Андрей Маркоянович
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- ПубликацияТолько метаданныеCompression and visualization of the operational parameters archive(2020) Zagrebayev, A.; Pilyugin, V.; Ten, S.; Загребаев, Андрей Маркоянович; Пилюгин, Виктор Васильевич© 2020 for this paper by its authors. Use permitted under Creative Commons License Attribution 4.0 International (CC BY 4.0).This article describes the mathematical apparatus for express analysis of the archive of operational parameters. 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 permitted values by parameters, 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.
- ПубликацияТолько метаданныеVisualization of the operational parameters archive of a nuclear reactor(2021) Ten, S.; Zagrebayev, A.; Pilyugin, V.; Загребаев, Андрей Маркоянович; Пилюгин, Виктор Васильевич© 2021 Copyright for this paper by its authors.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.
- ПубликацияТолько метаданныеVisualization of the neutron fields behavior according to the operational archives of the nuclear reactor RBMK(2021) Bukalin, A.; Zagrebayev, A.; Pilyugin, V.; Букалин, Алексей Олегович; Загребаев, Андрей Маркоянович; Пилюгин, Виктор Васильевич© 2021 Copyright for this paper by its authors.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.
- ПубликацияОткрытый доступCreation and visualization of an operational parameters archive(2021) Zagrebayev, A.; Ten, S.; Загребаев, Андрей Маркоянович© 2020 Elsevier B.V.. All rights reserved.The developed methodologies allow visualizing the behavior of limiting parameters over time and identifying patterns in the dynamics of changes in the parameters of a nuclear power unit, as 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 and visualization of data from the nuclear reactor archive using modern effective methodologies. Also, the development of new approaches to the analysis of archived data can improve the efficiency of power plant operators.
- ПубликацияОткрытый доступSimplified mathematical model and comparative analysis of possible ways of realizing the residual energy resource when decommissioning a channel-type reactor(2019) Zagrebayev, A.; Zaluzhnaya, G.; Naumov, V.; Загребаев, Андрей Маркоянович© 2019 Published under licence by IOP Publishing Ltd.We consider the problem of realization of the residual energy resource of fuel during decommissioning of the High-Power Channel-Type reactor. A mathematical model of the fuel assemblies spectrum for energy production is provided. Two methods of reactor decommissioning are compared. The first possible way to preserve the criticality of the reactor during decommission is the collapse of the core, when fuel assemblies with high energy production are discharged. The second possible way of decommissioning is formation of a two-zone loading: Fresh fuel assemblies are put in the centre, burnt out-on the periphery. It is shown that the second method gives a greater gain in power and unprocessed energy resources. The results are obtained on the point model of the fuel assemblies spectrum dynamics in the linear approximation of the with linear dependences of the power and the multiplication factor of FAs from energy productionn and indicate only the possibility of optimizing the fuel use in the process of removing the RBMK from service.