A candidate fusion engineering material, WC-FeCr

Samuel A. Humphry-Baker; Robert W. Harrison; Graeme Greaves; Alexander J. Knowles; George D.W. Smith; Stephen E. Donnelly; William E. Lee

doi:10.1016/j.scriptamat.2018.06.027

A candidate fusion engineering material, WC-FeCr

Samuel A. Humphry-Baker, Robert W. Harrison, Graeme Greaves, Alexander J. Knowles, George D.W. Smith, Stephen E. Donnelly, William E. Lee

Research output: Contribution to journal › Article › peer-review

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

Keywords

Cermets
Helium bubbles
Interface defects
Irradiation
Transmission electron microscopy

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

Access to Document

10.1016/j.scriptamat.2018.06.027

Cite this

@article{d3cdb5252a5047578ef664a4c68fe6d9,

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 BV",

}

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

U2 - 10.1016/j.scriptamat.2018.06.027

DO - 10.1016/j.scriptamat.2018.06.027

M3 - Article

SN - 1359-6462

VL - 155

SP - 129

EP - 133

JO - Scripta Materialia

JF - Scripta Materialia

ER -

A candidate fusion engineering material, WC-FeCr

Abstract

Keywords

UN SDGs

Access to Document

Fingerprint

Cite this