A candidate fusion engineering material, WC-FeCr

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

doi:10.1016/j.scriptamat.2018.06.027

A candidate fusion engineering material, WC-FeCr

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

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21 Citations (Scopus)

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.

Original language	English
Pages (from-to)	129-133
Number of pages	5
Journal	Scripta Materialia
Volume	155
Early online date	26 Jun 2018
DOIs	https://doi.org/10.1016/j.scriptamat.2018.06.027
Publication status	Published - 1 Oct 2018

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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.",

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T1 - A candidate fusion engineering material, WC-FeCr

AU - Humphry-Baker, Samuel

AU - Harrison, Robert

AU - Greaves, Graeme

AU - Knowles, Alexander

AU - Smith, George

AU - Donnelly, Stephen

AU - Lee, William

PY - 2018/10/1

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 - Interface defects

KW - Irradiation

KW - Helium bubbles

KW - Transmission electron microscopy

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DO - 10.1016/j.scriptamat.2018.06.027

M3 - Article

VL - 155

SP - 129

EP - 133

JO - Scripta Materialia

JF - Scripta Materialia

SN - 1359-6462

ER -

A candidate fusion engineering material, WC-FeCr

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