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Erosion and redeposition pattern on the W7-X graphite test divertor unit tile

Fortuna-Zalesna, Elzbieta ; Zielinski, Witold; Ciupiński, Łukasz; Spychalski, Maciej; Dhard, Chandra Prakash; Naujoks, Dirk; Rasinski, Marcin; Brezinsek, Sebastijan; W7-X Team 1
1 Institut für Hochleistungsimpuls- und Mikrowellentechnik (IHM), Karlsruher Institut für Technologie (KIT)

Abstract (englisch):

A set of plasma-facing components was retrieved f􀂘om the W7-X vessel afcer OPl.2b campaign with an inertially cooled Test Divertor Unit (TDU) and analyzed postmortem to provide data on the plasma-surface interactions processes in the complex device geometry. In ehe present study, the lower TDU horizontal target (HT) graphite tile HMl 9TM400hTE2 exposed to the plasma du ring both OP 1.2 campaigns was examined. The surface modification of the material caused by the plasma-wall interactions was determined. The study employed several microscopy mcthods including SEM, FIB, STEM, TEM, EDX, and optical profilomecry which showed that (i) distinct erosion zone was located at the inner HT strike line position, (ii) the area covered by a pronounced deposit was located adjacent the erosion zone, (iii) the target finger substructures positioned close to the outboard side was unaltered, and (iv) significant changes to surface roughness values along the length of the plate occurred.


Zugehörige Institution(en) am KIT Institut für Hochleistungsimpuls- und Mikrowellentechnik (IHM)
Publikationstyp Zeitschriftenaufsatz
Publikationsmonat/-jahr 06.2023
Sprache Englisch
Identifikator ISSN: 0920-3796
KITopen-ID: 1000159285
HGF-Programm 31.13.02 (POF IV, LK 01) Plasma Heating & Current Drive Systems
Erschienen in Fusion Engineering and Design
Verlag Elsevier
Band 191
Seiten Artkl.Nr.: 113589
Projektinformation EUROfusion (EU, EU 9. RP, 101052200)
Schlagwörter Wendelstein 7-X, Plasma-facing componems, Plasma-wall int.eraction, Erosion and deposition, Graphite
Nachgewiesen in Web of Science
Scopus
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