A candidate fusion engineering material, WC-FeCr

Samuel A. Humphry-Baker*, Robert W. Harrison, Graeme Greaves, Alexander J. Knowles, George D.W. Smith, Stephen E. Donnelly, William E. Lee

*Corresponding author for this work

Research output: Contribution to journalArticlepeer-review

8 Citations (Scopus)
151 Downloads (Pure)


A new candidate fusion engineering material, WC-FeCr, has been irradiated with He ions at 25 and 500 °C. Ions were injected at 6 keV to a dose of ~15 dpa and 50 at. % He, simulating direct helium injection from the plasma. The microstructural evolution was continuously characterised in situ using transmission electron microscopy. In the FeCr phase, a coarse array of 3–6 nm bubbles formed. In the WC, bubbles were less prominent and smaller (~2 nm). Spherical-cap bubbles formed at hetero-phase interfaces of tertiary precipitates, indicating that enhanced processing routes to minimise precipitation could further improve irradiation tolerance.

Original languageEnglish
Pages (from-to)129-133
Number of pages5
JournalScripta Materialia
Early online date26 Jun 2018
Publication statusPublished - 1 Oct 2018


  • Cermets
  • Helium bubbles
  • Interface defects
  • Irradiation
  • Transmission electron microscopy

ASJC Scopus subject areas

  • Materials Science(all)
  • Condensed Matter Physics


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