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Numerical simulation of neutral gas dynamics in the W7-X sub-divertor

W7-X Team 1; Varoutis, S. ORCID iD icon 2; Tantos, C. 2; Strobel, H. 3; Day, C. ORCID iD icon 3; Dhard, C. P.; Haak, V.; Igitkhanov, Y. 3; Naujoks, D.
1 Institut für Hochleistungsimpuls- und Mikrowellentechnik (IHM), Karlsruher Institut für Technologie (KIT)
2 Institut für Technische Physik (ITEP), Karlsruher Institut für Technologie (KIT)
3 Karlsruher Institut für Technologie (KIT)

Abstract (englisch):

The present work presents a 2D and 3D modeling of the neutral gas flow in the sub-divertor region of the W7-X. The investigations have been done using the DIVGAS code. The complex 2D and 3D geometries of the divertor components in the sub-divertor region have been considered and the Standard and High-Iota magnetic configurations have been numerically simulated. The main objective of this study is to investigate the dynamics of neutral particles in the sub-divertor region including the effects due to geometry and toroidal and poloidal leakages located at the divertor targets and baffles on the achieved pumping efficiency. A sensitivity analysis has been performed for the effect of various geometrical and flow parameters on the pumping performance, under different plasma scenarios. The considered incoming fluxes in the sub-divertor range between 1020 to 1022 (H2 s−1). The main conclusions, which can be extracted from the present numerical analysis could be summarized as follows; a large fraction of incoming neutral particle flux i.e. >70% on the low iota side and >40% for the high iota side is leaked back to the main divertor region, while higher incoming neutral fluxes facilitate the increase of the pumped flux as well as the decrease of the outflux. ... mehr


Verlagsausgabe §
DOI: 10.5445/IR/1000170894
Veröffentlicht am 24.05.2024
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Hochleistungsimpuls- und Mikrowellentechnik (IHM)
Institut für Technische Physik (ITEP)
Publikationstyp Zeitschriftenaufsatz
Publikationsmonat/-jahr 07.2024
Sprache Englisch
Identifikator ISSN: 0029-5515, 1741-4326
KITopen-ID: 1000170894
HGF-Programm 31.13.02 (POF IV, LK 01) Plasma Heating & Current Drive Systems
Erschienen in Nuclear Fusion
Verlag International Atomic Energy Agency (IAEA)
Band 64
Heft 7
Seiten 076011
Projektinformation EUROfusion (EU, EU 9. RP, 101052200)
Vorab online veröffentlicht am 22.05.2024
Schlagwörter Wendelstein 7-X, stellarator, particle exhaust, vacuum pumping, DSMC method, neutral gas dynamics
Nachgewiesen in Scopus
Web of Science
Dimensions
Globale Ziele für nachhaltige Entwicklung Ziel 7 – Bezahlbare und saubere Energie
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