Nuclear Materials and Energy (Aug 2017)

Remobilization of tungsten dust from castellated plasma-facing components

  • M. De Angeli,
  • P. Tolias,
  • S. Ratynskaia,
  • D. Ripamonti,
  • G. Riva,
  • S. Bardin,
  • T. Morgan,
  • G. De Temmerman

Journal volume & issue
Vol. 12
pp. 536 – 540

Abstract

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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.