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Remobilization of tungsten dust from castellated plasma-facing components
Author(s) -
M. De Angeli,
P. Tolias,
S. Ratynskaia,
D. Ripamonti,
G. Riva,
S. Bardin,
T.W. Morgan,
G. De Temmerman
Publication year - 2017
Publication title -
nuclear materials and energy
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 1.324
H-Index - 25
ISSN - 2352-1791
DOI - 10.1016/j.nme.2017.01.021
Subject(s) - tungsten , plasma , materials science , deposition (geology) , environmental science , composite material , metallurgy , physics , geology , nuclear physics , paleontology , sediment
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

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