A candidate fusion engineering material, WC-FeCr

Samuel Humphry-Baker, Robert Harrison, Graeme Greaves, Alexander Knowles, George Smith, Stephen Donnelly, William Lee

Research output: Contribution to journalArticle

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.
LanguageEnglish
Pages129-133
Number of pages5
JournalScripta Materialia
Volume155
Early online date26 Jun 2018
DOIs
Publication statusPublished - Oct 2018

Fingerprint

Fusion reactions
bubbles
fusion
engineering
Ions
Phase interfaces
Helium
Microstructural evolution
spherical caps
Precipitates
Irradiation
Transmission electron microscopy
Plasmas
precipitates
ions
Processing
helium
routes
injection
dosage

Cite this

Humphry-Baker, Samuel ; Harrison, Robert ; Greaves, Graeme ; Knowles, Alexander ; Smith, George ; Donnelly, Stephen ; Lee, William. / A candidate fusion engineering material, WC-FeCr. In: Scripta Materialia. 2018 ; Vol. 155. pp. 129-133.
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Humphry-Baker, S, Harrison, R, Greaves, G, Knowles, A, Smith, G, Donnelly, S & Lee, W 2018, 'A candidate fusion engineering material, WC-FeCr' Scripta Materialia, vol. 155, pp. 129-133. https://doi.org/10.1016/j.scriptamat.2018.06.027

A candidate fusion engineering material, WC-FeCr. / Humphry-Baker, Samuel; Harrison, Robert; Greaves, Graeme; Knowles, Alexander; Smith, George; Donnelly, Stephen; Lee, William.

In: Scripta Materialia, Vol. 155, 10.2018, p. 129-133.

Research output: Contribution to journalArticle

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AU - Humphry-Baker,Samuel

AU - Harrison,Robert

AU - Greaves,Graeme

AU - Knowles,Alexander

AU - Smith,George

AU - Donnelly,Stephen

AU - Lee,William

PY - 2018/10

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AB - 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.

KW - cermets

KW - interface defects

KW - irradiation

KW - helium bubbles

KW - transmission electron microscopy

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