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Кирнева, Наталья Александровна

Организационные подразделения

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Институт лазерных и плазменных технологий

Стратегическая цель Института ЛаПлаз – стать ведущей научной школой и ядром развития инноваций по лазерным, плазменным, радиационным и ускорительным технологиям, с уникальными образовательными программами, востребованными на российском и мировом рынке образовательных услуг.

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Кирнева

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Наталья Александровна

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Только метаданные
Possibility of Using the 140 GHz Frequency for ECR Plasma Heating in the T-15MD Tokamak
(2022) Kirneva, N. A.; Borshchegovskii, A. A.; Kuyanov, A. Yu.; Pimenov, I. S.; Roi, I. N.; Кирнева, Наталья Александровна
Только метаданные
On the Possibility of Applying ECR Heating and Current Drive in the DEMO-S and DEMO-FNS Facilities
(2023) Kirneva, N. A.; Кирнева, Наталья Александровна
Только метаданные
Microwave Setup of Amegawatt Power Level for the ECR Plasma Heating and Current Drive System of the T-15MD Tokamak
(2020) Denisov, G. G.; Malygin, V. I.; Tsvetkov, A. I.; Eremeev, A. G.; Kirneva, N. A.; Кирнева, Наталья Александровна
© 2021, Springer Science+Business Media, LLC, part of Springer Nature.As part of the creation of a unique T-15MD tokamak with a magnetic field of 2 T and an aspect ratio of 2.2, the first one of a series (8 pieces) of microwave setups of a megawatt power level for electron–cyclotron plasma heating and current drive was developed and successfully tested. The setup includes a gyrotron, power supplies, a microwave radiation transmission line, and a fast (response time is no more than 10 μs) gyrotron emergency protection system. The generation regime was experimentally demonstrated with the parameters 1 MW/30 s/82.6 GHz for an efficiency of 57%.
Только метаданные
A Variable Structure Control Scheme Proposal for the Tokamak a Configuration Variable
(2019) Marco, Aitor; Garrido, Aitor J.; Coda, Stefano; Garrido, Izaskun; Kirneva, N.; Кирнева, Наталья Александровна
Fusion power is the most significant prospects in the long-term future of energy in the sense that it composes a potentially clean, cheap, and unlimited power source that would substitute the widespread traditional nonrenewable energies, reducing the geographical dependence on their sources as well as avoiding collateral environmental impacts. Although the nuclear fusion research started in the earlier part of 20th century and the fusion reactors have been developed since the 1950s, the fusion reaction processes achieved have not yet obtained net power, since the generated plasma requires more energy to achieve and remain in necessary particular pressure and temperature conditions than the produced profitable energy. For this purpose, the plasma has to be confined inside a vacuum vessel, as it is the case of the Tokamak reactor, which consists of a device that generates magnetic fields within a toroidal chamber, being one of the most promising solutions nowadays. However, the Tokamak reactors still have several issues such as the presence of plasma instabilities that provokes a decay of the fusion reaction and, consequently, a reduction in the pulse duration. In this sense, since long pulse reactions are the key to produce net power, the use of robust and fast controllers arises as a useful tool to deal with the unpredictability and the small time constant of the plasma behavior. In this context, this article focuses on the application of robust control laws to improve the controllability of the plasma current, a crucial parameter during the plasma heating and confinement processes. In particular, a variable structure control scheme based on sliding surfaces, namely, a sliding mode controller (SMC) is presented and applied to the plasma current control problem. In order to test the validity and goodness of the proposed controller, its behavior is compared to that of the traditional PID schemes applied in these systems, using the RZIp model for the Tokamak a Configuration Variable (TCV) reactor. The obtained results are very promising, leading to consider this controller as a strong candidate to enhance the performance of the PID-based controllers usually employed in this kind of systems.
Только метаданные
Comparison of Operating Parameters of the KTM Tokamak with Operating Ranges of the Facility
(2023) Kirneva, N. A.; Belov, A. M.; Olkhovik, D. A.; Ryzhakov, D. V.; Кирнева, Наталья Александровна
Только метаданные
On the Choice of Electron Cyclotron Heating Frequency for T-15MD Tokamak
(2021) Kislov, D. A.; Roy, I. N.; Kirneva, N. A.; Кирнева, Наталья Александровна
© 2021, Pleiades Publishing, Ltd.Abstract: Electron cyclotron heating is one of the methods of additional plasma heating and noninductive current drive in the T-15MD tokamak. One to eight gyrotrons with a total power up to 7 MW will be used. The frequency of the microwave used depends on the parameters of the experimental scenarios in which the heating will be used and on the physical tasks for which it is intended. This article provides justification for the choice of the gyrotron frequency f1 ≅ 82.6 GHz for the start-up phase and for the first plasma experiments and considers the possibility of using this frequency at the stage of full-scale experiments. In order to provide flexibility of the Т-15MD ECH system, it is proposed to consider the possibility of the development of a gyrotron complex based on two-frequency gyrotrons with f1 ~ 82.6 GHz and f2 in the range of ~102–110 GHz.
Только метаданные
MODELING OF STABLE EQUILIBRIUM MAGNETIC CONFIGURATIONS FOR THE FIRST EXPERIMENTS ON THE TOKAMAK T-15MD INSTALLATION МОДЕЛИРОВАНИЕ УСТОИЧИВЫХ РАВНОВЕСНЫХ МАГНИТНЫХ КОНФИГУРАЦИИ ДЛЯ ПЕРВЫХ ЭКСПЕРИМЕНТОВ НА УСТАНОВКЕ ТОКАМАК Т-15МД
(2024) Sychugov, D. Yu.; Ryzhakov, D. V.; Andreev, V. F.; Gorbunov, A. V.; Kirneva, N. A.; Кирнева, Наталья Александровна
Только метаданные
Possibility of using the 140 GHZ frequency for ECR plasma heating in the T-15MD Tokamak ВОЗМОЖНОСТЬ ИСПОЛЬЗОВАНИЯ ЧАСТОТЫ 140 ГГЦ ДЛЯ ЭЦР-НАГРЕВА ПЛАЗМЫ В ТОКАМАКЕ Т-15МД
(2021) Borshchegovskii, A. A.; Kuyanov, A. Yu.; Pimenov, I. S.; Roi, I. N.; Kirneva, N. A.; Кирнева, Наталья Александровна
© 2021 National Research Center Kurchatov Institute. All rights reserved.Electron-cyclotron heating is one of the methods of additional plasma heating in the T-15MD tokamak. The article considers the possibility of plasma heating using an extraordinary wave on the third harmonic of electron-cyclotron resonance at a frequency of 140 GHz. It has been shown that in accordance with the calculations by quasi-linear OGRAY code, a high fraction of single-pass absorption (up to 96%) can be expected even when the ECR is turned on with an ohmic background. Increase of this fraction with the increase in plasma temperature agrees with the theoretical predictions. Vertical power launch seems to be most attractive. Possible engineering solutions for implementation of such a scheme are proposed.
Только метаданные
Working area of the mephist tokamak: Preliminar estimation ОБЛАСТЬ РАБОЧИХ ПАРАМЕТРОВ ТОКАМАКА МИФИСТ: ПРЕДВАРИТЕЛЬНАЯ ОЦЕНКА
(2020) Kirneva, N. A.; Vorobjev, G. M.; Ganin, S. A.; Drozd, A. S.; Kudashev, I. S.; Kulagin, V. V.; Kurnaev, V. A.; Кирнева, Наталья Александровна; Дрозд, Алексей Станиславович; Кулагин, Владимир Владимирович
© 2020 National Research Center Kurchatov Institute. All rights reserved.Small spherical tokamak MEPHIST is under construction at the NRNU MEPhI. This paper is devoted to the analysis of the working area of the MEPHIST tokamak and modeling of ohmic discharges in the different plasma configurations, which can be obtained in it.
Только метаданные
PHYSICAL RESEARCH PROGRAM ON THE T-15MD TOKAMAK ПРОГРАММА ФИЗИЧЕСКИХ ИССЛЕДОВАНИИ НА ТОКАМАКЕ Т-15МД
(2024) Velikhov, E. P.; Kovalchuk, M. V.; Anashkin, I. O.; Kirneva, N. A.; Kuteev, B. V.; Marenkov, E. D.; Melnikov, A. V.; Кирнева, Наталья Александровна; Кутеев, Борис Васильевич; Маренков, Евгений Дмитриевич; Мельников, Александр Владимирович