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Napájecí soustava s pulsním generátorem pro tokamak COMPASS D
Antl, Marek ; Prošek, Jan (oponent) ; Drápela, Jiří (vedoucí práce)
Jeden z možných způsobů, jak zajistit do dalších let nezbytnou elektrickou energii je pomocí termojaderné syntézy. Zařízení, které se zabývá touto problematikou se nazývá stellarátor nebo tokamak. V této mé práci uvádím princip činnosti tokamaku a jeho postupný vývoj s náhledem na budoucnost. Přesněji se zabývám konkrétním tokamakem, který byl převezen z Culhamu do Prahy a jeho zdrojem napájení, který musel být nově navržen. Jedná se o tokamak COMPASS D. Zaměření mé práce spočívá v části napájení cívek tokamaku a energetické prvky v jeho napájecí cestě. Jedná se však jen o zkušební zařízení, které má ještě dlouhou cestu před sebou ke zdárnému konci, kterým je dodávání elektrické energie ve větší míře než je energie spotřebovaná. V současné době jde pouze o zkušební zařízení, na kterém se provádějí testy a různé zkoušky. Výsledky těchto zkoušek budou použity pro další bádání a povedou k lepším výsledkům tohoto i jiných zařízení.
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Poisson Equation Solver Parallelisation for Particle-in-Cell Model
Podolník, Aleš ; Komm, Michael ; Dejarnac, Renaud ; Gunn, J. P.
Numerical simulations based on PIC technique like the SPICE2 model developed at IPP ASCR are often used in tokamak plasma physics to investigate the interaction of edge plasma with plasma-facing components. The SPICE2 model has been parallelised with the exception of the Poisson equation solver which considerably slows down the simulations. It is now being upgraded to a parallelised version to be efficient enough to perform more demanding tasks like the ITER tokamak baseline scenario edge plasma whose conditions like high density (up to 1020 m−3) and low temperature (1–2 eV) result in simulations taking several months to compute. Performance and scaling are compared for different cases in order to choose the optimal candidate for aforementioned applications.
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Plasma Boundary Reconstruction using Fast Camera on the COMPASS Tokamak
Háček, Pavel ; Berta, Miklós ; Stöckel, Jan ; Weinzettl, Vladimír ; Budai, C. ; Szabolics, T. ; Bencze, A.
Determination of the plasma boundary is an important task for safe operation of the tokamak and diagnostic systems as well as for correct interpretation of the measured data. Magnetic reconstruction codes routinely used to determine the shape of the plasma have a number of limitations which can make the reconstruction problematic. Recently, it has been demonstrated on several devices that it is possible to provide independent measurement of the plasma boundary by observation of the visiblelight emission using fast framing cameras. In the presented work, a single fast camera on the COMPASS tokamak was used for reconstruction of the optical plasma boundary, assuming a toroidally symmetric visible-light emission profile located in the edge of plasma. As a first result, application of the method on D-shaped COMPASS shot 7145 and its comparison with magnetic reconstruction from the EFIT code is given. Both methods show good agreement with average difference 0.5 cm.
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Study of Alfven Eigenmodes in Tokamak COMPASS
Markovič, Tomáš ; Stöckel, Jan ; Seidl, Jakub ; Melnikov, A. ; Medvedev, S.
Having both MHD and kinetic character plasma Alfven eigenmodes are signicant not only on the eld basic plasma research, but also on the eld of magnetic connement fusion. An introduction to basic physical principles of Alfven eigenmodes under MHD approximation is provided. Presented results of recent experiments on COMPASS suggest occurrence of toroidal Alfven eigenmodes in this tokamak, which is further supported by preliminary linear MHD code simulations, althought more studies will have to be conducted in the future to further investigate presented modes therein.
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Parallel Heat Flux Decay Length Study in the COMPASS Tokamak Using MWIR and LWIR Cameras
Vondráček, Petr ; Horáček, Jan ; Pánek, Radomír ; Gauthier, E.
A comprehensive study of a parallel heat flux in a tokamak scrape-off layer (SOL) has been performed in the COMPASS tokamak recently. Specially shaped high field side (HFS) limiter was used to estimate a heat flux radial decay length for small limiter radial misalignment. Long wavelength IR microbolometer and medium wavelength IR InSb camera were used for this purpose. This paper compares results obtained by the means of both cameras and demonstrates observation of very narrow heat flux decay length close to the last closed flux surface (LCFS) independantly on used camera.
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