Remobilization of tungsten dust from castellated plasma-facing components

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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.

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De Angeli, M., Tolias, P., Ratynskaia, S., Ripamonti, D., Riva, G., Bardin, S., … De Temmerman, G. (2017). Remobilization of tungsten dust from castellated plasma-facing components. Nuclear Materials and Energy, 12, 536–540. https://doi.org/10.1016/j.nme.2017.01.021

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