A candidate fusion engineering material, WC-FeCr

Research output: Contribution to journalArticlepeer-review

Authors

  • Samuel A. Humphry-Baker
  • Robert W. Harrison
  • Graeme Greaves
  • George D.W. Smith
  • Stephen E. Donnelly
  • William E. Lee

Colleges, School and Institutes

External organisations

  • Imperial College London
  • University of Huddersfield
  • Tokamak Energy Ltd
  • Bangor University

Abstract

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.

Details

Original languageEnglish
Pages (from-to)129-133
Number of pages5
JournalScripta Materialia
Volume155
Early online date26 Jun 2018
Publication statusPublished - 1 Oct 2018

Keywords

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