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 ...
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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-29181461 |
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.