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The ECRH-Power Upgrade at the Wendelstein 7-X Stellarator

W7-X Team 1; Laqua, H. P.; Avramidis, K. A.; Braune, H.; Chelis, I.; Gantenbein, G. 1; Illy, S. 1; Ioannidis, Z.; Jelonnek, J. 1; Jin, J. 1; Krier, L. ORCID iD icon 1; Lechte, C.; Leggieri, A.; Legrand, F.; Marsen, S.; Moseev, D.; Oosterbeek, H.; Rzesnicki, T. 1; Ruess, T. ORCID iD icon 1; ... mehr

Abstract (englisch):

The existing ECRH system at W7-X consists of 10 gyrotrons, with output power levels ranging from 0.6 MW up to 1.0 MW each at a frequency of 140 GHz, quasi-optical transmission lines and microwave launchers at the plasma vessel. Compared to other large fusion experiments, W7-X has a relatively low power-to-volume ratio. However high heating power is particularly necessary for achieving high plasma beta values, where the improved confinement of fast ions, one of the optimization criteria of W7-X, can be examined. It is therefore necessary to expand the ECRH systems in several consecutive steps. It is planned to increase the number of gyrotron positions from 10 to 12 and at the same time to evolve the gyrotron output power in several development steps from 1 MW to nominal 1.5 MW and, finally, up to 2 MW. At the same time, the transmission lines will also be upgraded for 2 MW operation. A special effort is also made to improve the reliability of the system by the fast control system.


Verlagsausgabe §
DOI: 10.5445/IR/1000156433
Veröffentlicht am 02.03.2023
Originalveröffentlichung
DOI: 10.1051/epjconf/202327704003
Dimensions
Zitationen: 3
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Hochleistungsimpuls- und Mikrowellentechnik (IHM)
Publikationstyp Zeitschriftenaufsatz
Publikationsjahr 2023
Sprache Englisch
Identifikator ISSN: 2100-014X
KITopen-ID: 1000156433
HGF-Programm 31.13.02 (POF IV, LK 01) Plasma Heating & Current Drive Systems
Erschienen in EPJ Web of Conferences
Verlag EDP Sciences
Band 277
Seiten Art.-Nr.: 04003
Vorab online veröffentlicht am 23.02.2023
Schlagwörter W7-X; ECRH
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