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TCV Team

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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.
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The role of plasma-molecule interactions on power and particle balance during detachment on the TCV tokamak
(2021) Verhaegh, K.; Lipschultz, B.; Harrison, J. R.; Duval, B. P.; Kukushkin, A.; Pshenov, A.
This paper shows experimental results from the TCV tokamak that indicate plasma-molecule interactions involving D2+ D-2(+) + D rate. The converged SOLPS-ITER simulations are post-processed with alternative reaction rates, resulting in considerable contributions of D-2(+) to particle and power losses as well as dissociation below the D-2 dissociation area. Those findings are in quantitative agreement with the experimental results.
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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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Токамак с переменной конфигурацией ( TCV , буквально «токамак с переменной конфигурацией») — экспериментальный токамак , расположенный в Швейцарском центре плазмы (SPC) Федеральной политехнической школы Лозанны (EPFL) в Лозанне , Швейцария . Токамак TCV , являющийся крупнейшей экспериментальной установкой Швейцарского плазменного центра, исследует физику термоядерного синтеза с магнитным удержанием . Он отличается от других токамаков своей специализированной способностью формирования плазмы , которая может создавать плазму различных форм без необходимости модификаций оборудования. Исследования, проведенные на TCV, способствуют пониманию физики ИТЭР и будущих термоядерных электростанций, таких как DEMO . В настоящее время он является частью программы токамака среднего размера (MST) EUROfusion наряду с ASDEX Upgrade , MAST Upgrade и WEST .
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