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Remobilization of tungsten dust from castellated plasma-facing components

De Angeli, M. (author)
Tolias, Panagiotis, 1984- (author)
KTH,Rymd- och plasmafysik
Ratynskaia, Svetlana V. (author)
KTH,Rymd- och plasmafysik
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Ripamonti, D. (author)
Riva, G. (author)
Bardin, S. (author)
Morgan, T. (author)
De Temmerman, G. (author)
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 (creator_code:org_t)
Elsevier BV, 2017
2017
English.
In: NUCLEAR MATERIALS AND ENERGY. - : Elsevier BV. - 2352-1791. ; 12, s. 536-540
  • Journal article (peer-reviewed)
Abstract Subject headings
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  • 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.

Subject headings

NATURVETENSKAP  -- Fysik -- Fusion, plasma och rymdfysik (hsv//swe)
NATURAL SCIENCES  -- Physical Sciences -- Fusion, Plasma and Space Physics (hsv//eng)

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