A candidate fusion engineering material, WC-FeCr

Research output: Contribution to journalArticlepeer-review

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

In: Scripta Materialia, Vol. 155, 01.10.2018, p. 129-133.

Research output: Contribution to journalArticlepeer-review

Harvard

Humphry-Baker, SA, Harrison, RW, Greaves, G, Knowles, AJ, Smith, GDW, Donnelly, SE & Lee, WE 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

APA

Humphry-Baker, S. A., Harrison, R. W., Greaves, G., Knowles, A. J., Smith, G. D. W., Donnelly, S. E., & Lee, W. E. (2018). A candidate fusion engineering material, WC-FeCr. Scripta Materialia, 155, 129-133. https://doi.org/10.1016/j.scriptamat.2018.06.027

Vancouver

Humphry-Baker SA, Harrison RW, Greaves G, Knowles AJ, Smith GDW, Donnelly SE et al. A candidate fusion engineering material, WC-FeCr. Scripta Materialia. 2018 Oct 1;155:129-133. https://doi.org/10.1016/j.scriptamat.2018.06.027

Author

Humphry-Baker, Samuel A. ; Harrison, Robert W. ; Greaves, Graeme ; Knowles, Alexander J. ; Smith, George D.W. ; Donnelly, Stephen E. ; Lee, William E. / A candidate fusion engineering material, WC-FeCr. In: Scripta Materialia. 2018 ; Vol. 155. pp. 129-133.

Bibtex

@article{d05af4b5670440988fb14a40f12592fa,
title = "A candidate fusion engineering material, WC-FeCr",
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.",
keywords = "Cermets, Helium bubbles, Interface defects, Irradiation, Transmission electron microscopy",
author = "Humphry-Baker, {Samuel A.} and Harrison, {Robert W.} and Graeme Greaves and Knowles, {Alexander J.} and Smith, {George D.W.} and Donnelly, {Stephen E.} and Lee, {William E.}",
year = "2018",
month = oct,
day = "1",
doi = "10.1016/j.scriptamat.2018.06.027",
language = "English",
volume = "155",
pages = "129--133",
journal = "Scripta Materialia",
issn = "1359-6462",
publisher = "Elsevier",

}

RIS

TY - JOUR

T1 - A candidate fusion engineering material, WC-FeCr

AU - Humphry-Baker, Samuel A.

AU - Harrison, Robert W.

AU - Greaves, Graeme

AU - Knowles, Alexander J.

AU - Smith, George D.W.

AU - Donnelly, Stephen E.

AU - Lee, William E.

PY - 2018/10/1

Y1 - 2018/10/1

N2 - 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.

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 - Helium bubbles

KW - Interface defects

KW - Irradiation

KW - Transmission electron microscopy

UR - http://www.scopus.com/inward/record.url?scp=85048952247&partnerID=8YFLogxK

U2 - 10.1016/j.scriptamat.2018.06.027

DO - 10.1016/j.scriptamat.2018.06.027

M3 - Article

AN - SCOPUS:85048952247

VL - 155

SP - 129

EP - 133

JO - Scripta Materialia

JF - Scripta Materialia

SN - 1359-6462

ER -