Advanced tungsten materials for plasma-facing components of DEMO and fusion power plants

R. Neu, J. Riesch, J. W. Coenen, J. Brinkmann, A. Calvo, S. Elgeti, C. García-Rosales, H. Greuner, T. Hoeschen, G. Holzner, F. Klein, F. Koch, Ch Linsmeier, A. Litnovsky, T. Wegener, S. Wurster, J. H. You

Research output: Contribution to journalArticlepeer-review

82 Scopus citations

Abstract

Tungsten is the major candidate material for the armour of plasma facing components in future fusion devices. To overcome the intrinsic brittleness of tungsten, which strongly limits its operational window, a W-fibre enhanced W-composite material (Wf/W) has been developed incorporating extrinsic toughening mechanisms. Small Wf/W samples show a large increase in toughness. Recently, a large sample (50 mm × 50 mm × 3 mm) with more than 2000 long fibres has been successfully produced allowing further mechanical and thermal testing. It could be shown that even in a fully embrittled state, toughening mechanisms as crack bridging by intact fibres, as well as the energy dissipation by fibre-matrix interface debonding and crack deflection are still effective. A potential problem with the use of pure W in a fusion reactor is the formation of radioactive and highly volatile WO3 compounds and their potential release under accidental conditions. It has been shown that the oxidation of W can be strongly suppressed by alloying with elements forming stable oxides. WCr10Ti2 alloy has been produced on a technical scale and has been successfully tested in the high heat flux test facility GLADIS. Recently, W-Cr-Y alloys have been produced on a lab-scale. They seem to have even improved properties compared to the previously investigated W alloys.

Original languageEnglish
Pages (from-to)1046-1052
Number of pages7
JournalFusion Engineering and Design
Volume109-111
DOIs
StatePublished - 1 Nov 2016

Keywords

  • (Extrinsic) toughening
  • Composite materials
  • Plasma facing components
  • Self-passivating alloys
  • Tungsten

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