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3D numerical study of neutral gas dynamics in the DTT particle exhaust using the DSMC method

Tantos, C. 1; Varoutis, S. ORCID iD icon 1; Hauer, V. 1; Day, C. ORCID iD icon 1; Innocente, P.
1 Institut für Technische Physik (ITEP), Karlsruher Institut für Technologie (KIT)

Abstract:

Recently the design of the divertor tokamak test (DTT) Facility divertor has been modified and consolidated. The new divertor design presents significant geometrical differences compared to the previous ITER-like one, including the presence of a more flattened dome shape. This paper presents a complete 3D numerical analysis of the neutral gas dynamics inside the DTT subdivertor area for the latest divertor design. The analysis has been performed based on the direct simulation Monte Carlo method by applying the DIVGAS simulator code. SOLEDGE2D-EIRENE plasma simulations have been performed for a deuterium plasma scenario at the maximum additional power in partially detached condition achieved by neon impurity seeding and the extracted information about the neutral particles has been imposed as incoming boundary conditions. The pumping efficiency of the DTT divertor is examined by considering various cases with respect to the pumping probability and the effect of the toroidal and poloidal leakages is quantified. The results show that a significant percentage of the incoming flux of neutrals returns back to the plasma site through the entry gaps (60% for deuterium and 40% for neon), and, consequentially, only a small percentage (∼2%–15%) of the incoming flux can be pumped out from the system. ... mehr


Verlagsausgabe §
DOI: 10.5445/IR/1000165832
Veröffentlicht am 19.12.2023
Originalveröffentlichung
DOI: 10.1088/1741-4326/ad0c80
Scopus
Zitationen: 2
Web of Science
Zitationen: 1
Dimensions
Zitationen: 2
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Technische Physik (ITEP)
Publikationstyp Zeitschriftenaufsatz
Publikationsmonat/-jahr 01.2024
Sprache Englisch
Identifikator ISSN: 0029-5515, 1741-4326
KITopen-ID: 1000165832
HGF-Programm 31.13.01 (POF IV, LK 01) Ex-Vessel Plant Systems & Engineering
Erschienen in Nuclear Fusion
Verlag International Atomic Energy Agency (IAEA)
Band 64
Heft 1
Seiten Art.-Nr.: 016019
Projektinformation EUROfusion (EU, EU 9. RP, 101052200)
Vorab online veröffentlicht am 24.11.2023
Schlagwörter divertor tokamak test facility (DTT), vacuum pumping, DSMC method, particle exhaust, SolEdge2D-Eirene, pumped fluxes, neutral gas dynamics
Nachgewiesen in Web of Science
Dimensions
Scopus
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