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2021•Fusion Engineering and DesignOpen access

Preliminary design of the COMPASS upgrade tokamak

Petr Vondracek, R. Pánek, M. Hron, J. Havlíček, V. Weinzettl, T. N. Todd, David Tskhakaya, Geof Cunningham, Pavel Háček, Jakub Hromádka, P. Junek, Jaroslav Krbec, Nisarg Patel, David Sestak, Jozef Varju, Jiřı́ Adámek, M. Balazsova, Vojtech Balner, Petr Barton, J. Bielecki, P. Bílková, J. Błocki, Dariusz Bocian, K. Bogár, O. Bogár, P. Boocz, I. Borodkina, A. Russell Brooks, P. Böhm, J. Burant, A. Casolari, J. Cavalier, P. Chappuis, R. Dejarnac, Mashenka B. Dimitrova, M. Dudak, I. Ďuran, Robert A. Ellis, Slavomír Entler, Jiarong Fang, M. Farník, O. Ficker, David Fridrich, Š. Fuková, J. Gérardin, I. Hanák, Antonín Havránek, A. Herrmann, Jan Horáček, O. Hronova, M. Imríšek, N. Isernia, Fabien Jaulmes, Martin Jeřáb, Vladimír Kindl, M. Komm, Karel Kovařík, M. Kral, L. Kripner, E. Macúšová, T. Majer, Tomáš Markovič, E. Matveeva, Katarzyna Mikszuta-Michalik, M. Mohelnik, I. Mysiura, D. Naydenkova, I. Nemec, Rafał Ortwein, Karel Patocka, M. Peterka, A. Podolník, Filip Procházka, Jan Prevratil, Jan Řeboun, Valentino Scalera, Marek Scholz, Jakub Svoboda, Jacek Świerblewski, Miroslav Sos, M. Tadros, P. Titus, Matej Tomes, A. Torres, Grzegorz Tracz, Pavel Turjanica, M. Varavin, Viktor Veselovsky, F. Villone, Przemysław Wąchal, Vadim Yanovskiy, G. Zadvitskiy, J. Zaja̧c, A. R. Zak, Dobromil R. Zaloga, Jan Zelda, Han Zhang

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Abstract

COMPASS Upgrade is a new medium size, high magnetic field tokamak (R = 0.9 m, Bt = 5 T, Ip = 2 MA) currently under design in the Czech Republic. It will provide unique capabilities for addressing some of the key challenges in plasma exhaust physics, advanced confinement modes and advanced plasma configurations as well as testing new plasma facing materials and liquid metal divertor concepts. This paper contains an overview of the preliminary engineering design of the main systems of the COMPASS Upgrade tokamak (vacuum vessel, central solenoid and poloidal field coils, toroidal field coils, support structure, cryostat, cryogenic system, power supply system and machine monitoring and protection system). The description of foreseen auxiliary plasma heating systems and plasma diagnostics is also provided as well as a summary of expected plasma performance and available plasma configurations.

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What this paper is about

COMPASS Upgrade is a new medium size, high magnetic field tokamak (R = 0.9 m, Bt = 5 T, Ip = 2 MA) currently under design in the Czech Republic. It will provide unique capabilities for addressing some of the key challenges in plasma exhaust physics, advanced confinement modes and advanced plasma configurations as well as testing new plasma facing materials and liquid metal divertor concepts. This paper contains an overview of the preliminary engineering design of the main systems of the COMPASS Upgrade tokamak (vacuum vessel, central solenoid and poloidal field coils, toroidal field coils, support structure, cryostat, cryogenic system, power supply system and machine monitoring and protection system). The description of foreseen auxiliary plasma heating systems and plasma diagnostics is also provided as well as a summary of expected plasma performance and available plasma configurations.

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Available abstract

COMPASS Upgrade is a new medium size, high magnetic field tokamak (R = 0.9 m, Bt = 5 T, Ip = 2 MA) currently under design in the Czech Republic. It will provide unique capabilities for addressing some of the key challenges in plasma exhaust physics, advanced confinement modes and advanced plasma configurations as well as testing new plasma facing materials and liquid metal divertor concepts. This paper contains an overview of the preliminary engineering design of the main systems of the COMPASS Upgrade tokamak (vacuum vessel, central solenoid and poloidal field coils, toroidal field coils, support structure, cryostat, cryogenic system, power supply system and machine monitoring and protection system). The description of foreseen auxiliary plasma heating systems and plasma diagnostics is also provided as well as a summary of expected plasma performance and available plasma configurations.

Key concepts: Tokamak, Divertor, Upgrade, Cryostat, Nuclear engineering, Plasma, Compass, Solenoid

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