Научная группа: Группа «Элементы и системы автоматики» (Кафедра №13, ИЯФиТ)
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A thermohydraulic flow loop for developing novel solutions in the field of using digital twins for nuclear power facilities
(2020) Laouar, S.; Delov, M. I.; Litvintsova, Yu. E.; Kuzmenkov, D. M.; Muradyan, K. Yu.; Navasardyan, M. V.; Kutsenko, K. V.; Делов, Максим Игоревич; Кузьменков, Дмитрий Михайлович; Мурадян, Карен Юрикович; Куценко, Кирилл Владленович
© 2020 Obninsk Institute for Nuclear Power Engineering, National Research Nuclear University 'MEPhI'. All rights reserved.The experience is presented in building a thermohydraulic flow loop for developing technical and software solutions in using digital twins of nuclear equipment. The thermohydraulic flow loop was developed and manufactured at National Research Nuclear University MEPhI and represents a two-loop facility that allows investigating the processes of heat and mass exchange at forced and natural water circulation modes. The experimental facility allows one to obtain new data on heat transfer and hydrodynamics of two-phase flows round the fuel element bundles required for verification of computer codes. The obtained preliminary experimental results agree well with the calculations based on various codes. As part of building a digital twin for the thermohydraulic flow loop, a system is developed to diagnose, control and monitor heat-exchange transients based on physically justified real-time techniques. Neural network technologies will make it possible to predict changes in the flow loop's thermohydraulic parameters in response to external impacts. Further, a virtual prototype of the experimental facility is expected to be used in the training process and for distance learning.
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Visualization of the BREST-OD-300 RP FA assembly and inspection area using virtual reality technologies
(2025) Tolokonskiy, A. O.; Kovalionok, D. G.; Толоконский, Андрей Олегович; Ковалёнок, Денис Геннадьевич
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Active disturbance rejection control of pressurized water reactor
(2023) Ahmad, S.; Abdulraheem, K. K.; Tolokonsky, A. O.; Ahmed, H.; Толоконский, Андрей Олегович
Control design for pressurized water reactor (PWR) is difficult due to associated non-linearity, modelling uncertainties and time-varying system parameters. Extended state observer (ESO) based active disturbance rejection control (ADRC) presents a simple and robust solution which is almost model free and has few tuning parameters. However, conventional ESO suffers from noise over-amplification in the obtained estimates due to high-gain construction which in turn degrades the noise sensitivity of the closed-loop system and limits the achievable dynamic performance in practical scenarios. To overcome this problem, two recent techniques namely cascade ESO (CESO) and low-power higher-order ESO (LHESO) are implemented for control of PWR. Simulation analysis is conducted in MATLAB to illustrate the performance improvement obtained over conventional ESO based ADRC, particularly in case of time-varying disturbances. Extensive simulation analysis is also conducted to investigate robustness towards parametric uncertainties. The study also presents a comparison of conventional ESO, CESO and LHESO to highlight their advantages as well as limitations which in turn would help the users in selecting the appropriate scheme for their particular use-case.
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Modelling and simulating of a multiple input and multiple output system to control the liquid level and temperature by using model predictive control
(2020) Laidani, Z.; Tolokonsky, A. O.; Abdulraheem, K. K.; Ouahioune, M.; Berreksi, R.; Толоконский, Андрей Олегович
© Published under licence by IOP Publishing Ltd.In recent years, Model Predictive Control has been regarded as one of the most reliable advanced control methods widely used in industrial and nuclear processes. Model predictive control uses a system model to forecast its future response, and also treats a real-time optimization algorithm to choose the best control action that leads the predicted output to the reference. The overall design goal of a predictive control model is to compute the trajectory of a future manipulated variable input signal to optimize the future behavior of the plant output. Optimization is performed within a limited time window by providing information at the beginning of the time window. This paper proposes a predictive controller MPC model for multiple input-output systems. The design of the controller includes the development of a model of the state space system for the tank system, then the design and the simulation of the MPC controller for the developed model system. The variables to be controlled are the temperature and the liquid level of the tank by changing the MPC's parameters.
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Concept of instrumentation of digital twins of nuclear power plants units as observers for digital NPP I&C system
(2019) Volodin, V. S.; Tolokonskii, A. O.; Толоконский, Андрей Олегович
© 2019 IOP Publishing Ltd.The relevance of the idea under consideration lies in the development of the use of digital twins of power units in the nuclear industry. With their help, we can not only predict the state of technological equipment, etc., but also solve the problem of parameter tuning of automatic regulators in different operating modes of NPP unit. Authors consider approaches to this problem based on optimal control theory, fuzzy logic and machine learning. Advantages and disadvantages of each approach are considered.
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Институт ядерной физики и технологий
Цель ИЯФиТ и стратегия развития - создание и развитие научно-образовательного центра мирового уровня в области ядерной физики и технологий, радиационного материаловедения, физики элементарных частиц, астрофизики и космофизики.
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Направления исследований:
- Перспективные технологии управления
Разработка многоконтурных систем управления на базе нечеткой логики для сложных динамических объектов управления
- Разработка и верификация программного обеспечения автоматизированных систем управления
технологическими процессами
Разработка алгоритмов и верификация программного обеспечения автоматических регуляторов энергоблоков АЭС
- Автоматизация исследовательских стендов
Разработка систем управления и автоматизации для исследовательских теплогидравлических и критических стендов в НИЯУ МИФИ и НИЦ «Курчатовский институт»