Preliminary design of the COMPASS upgrade tokamak

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 con...

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Veröffentlicht in:	Fusion engineering and design 2021-08, Vol.169 (C), p.112490, Article 112490
Hauptverfasser:	Vondracek, P., Panek, R., Hron, M., Havlicek, J., Weinzettl, V., Todd, T., Tskhakaya, D., Cunningham, G., Hacek, P., Hromadka, J., Junek, P., Krbec, J., Patel, N., Sestak, D., Varju, J., Adamek, J., Balazsova, M., Balner, V., Barton, P., Bielecki, J., Bilkova, P., Błocki, J., Bocian, D., Bogar, K., Bogar, O., Boocz, P., Borodkina, I., Brooks, A., Bohm, P., Burant, J., Casolari, A., Cavalier, J., Chappuis, P., Dejarnac, R., Dimitrova, M., Dudak, M., Duran, I., Ellis, R., Entler, S., Fang, J., Farnik, M., Ficker, O., Fridrich, D., Fukova, S., Gerardin, J., Hanak, I., Havranek, A., Herrmann, A., Horacek, J., Hronova, O., Imrisek, M., Isernia, N., Jaulmes, F., Jerab, M., Kindl, V., Komm, M., Kovarik, K., Kral, M., Kripner, L., Macusova, E., Majer, T., Markovic, T., Matveeva, E., Mikszuta-Michalik, K., Mohelnik, M., Mysiura, I., Naydenkova, D., Nemec, I., Ortwein, R., Patocka, K., Peterka, M., Podolnik, A., Prochazka, F., Prevratil, J., Reboun, J., Scalera, V., Scholz, M., Svoboda, J., Swierblewski, J., Sos, M., Tadros, M., Titus, P., Tomes, M., Torres, A., Tracz, G., Turjanica, P., Varavin, M., Veselovsky, V., Villone, F., Wąchal, P., Yanovskiy, V., Zadvitskiy, G., Zajac, J., Zak, A., Zaloga, D., Zelda, J., Zhang, H.
Format:	Artikel
Sprache:	eng
Schlagworte:	COMPASS-U Configurations Cryogenic equipment Design engineering Field coils Heating systems High magnetic field Liquid metals Plasma Plasma diagnostics Plasma heating Preliminary designs Solenoids Thermonuclear fusion Tokamak design Tokamak devices
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Beschreibung
Zusammenfassung:	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.
ISSN:	0920-3796 1873-7196
DOI:	10.1016/j.fusengdes.2021.112490