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.
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