|Title||Remobilization of tungsten dust from castellated plasma-facing components|
|Publication Type||Journal Article|
|Year of Publication||2017|
|Authors||M. de Angeli, P. Tolias, S. Ratynskaia, D. Ripamonti, G. Riva, S. Bardin, T. Morgan, G. De Temmerman|
|Journal||Nuclear Materials and Energy|
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.
|Alternate Title||Nucl. Mater. Energy|
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