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Remobilization of tungsten dust from castellated plasma-facing components

Author
Abstract

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.

Year of Publication
2017
Journal
Nuclear Materials and Energy
Volume
12
Number of Pages
536-540
Date Published
08/2017
DOI
10.1016/j.nme.2017.01.021
PId
9d971e0697b4e85cc20d34f17d72e93e
Alternate Journal
Nucl. Mater. Energy
Label
OA
Journal Article
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