Remobilization of tungsten dust from castellated plasma-facing components

Studies of tungsten dust remobilization from castellated plasma-facing components can shed light to whether gaps constitute a dust accumulation site with important implications for monitoring but also removal. Castellated structures of ITER relevant geometry that contained pre-adhered tungsten dust of controlled deposition profile have been exposed in the Pilot-PSI linear device. The experiments were performed under steady state and transient plasma conditions, as well as varying magnetic field topologies. The results suggest that dust remobilization from the plasma-facing monoblock surface ca... Mehr ...

Verfasser: D. Ripamonti
G. Riva
G. De Temmerman
M. De Angeli
Svetlana V. Ratynskaia
S. Bardin
Thomas Hunt Morgan
Panagiotis Tolias
Dokumenttyp: Artikel
Erscheinungsdatum: 2017
Schlagwörter: H2020 / Netherlands / EC / European Commission / Energy Research / COFUND (European Joint Programme) / Nuclear Energy and Engineering / Materials Science (miscellaneous) / Nuclear and High Energy Physics
Sprache: Englisch
Permalink: https://search.fid-benelux.de/Record/base-27200767
Datenquelle: BASE; Originalkatalog
Powered By: BASE
Link(s) : https://www.openaccessrepository.it/record/86767

Studies of tungsten dust remobilization from castellated plasma-facing components can shed light to whether gaps constitute a dust accumulation site with important implications for monitoring but also removal. Castellated structures of ITER relevant geometry that contained pre-adhered tungsten dust of controlled deposition profile have been exposed in the Pilot-PSI linear device. The experiments were performed under steady state and transient plasma conditions, as well as varying magnetic field topologies. The results suggest that dust remobilization from the plasma-facing monoblock surface can enhance dust trapping in the gaps and that tungsten dust is efficiently trapped inside the gaps.