A candidate fusion engineering material, WC-FeCr
File(s)
Publlished version
Author(s)
Type
Journal Article
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.
Date Issued
2018-10-01
Date Acceptance
2018-06-10
Citation
Scripta Materialia, 2018, 155, pp.129-133
ISSN
1359-6462
Publisher
Elsevier
Start Page
129
End Page
133
Journal / Book Title
Scripta Materialia
Volume
155
Copyright Statement
© 2018 Acta Materialia Inc. Published by Elsevier Ltd. This is an open access article under the CC BY license (http://creativecommons.org/licenses/by/4.0/)
Sponsor
Tokamak Energy Ltd
Grant Number
PO TE140409-1
Subjects
0912 Materials Engineering
0913 Mechanical Engineering
Materials
Publication Status
Published
Date Publish Online
2018-06-26