A candidate fusion engineering material, WC-FeCr

SCRIPTA MATERIALIA

卷:155

Article

Humphry-Baker, Samuel A.¹  Harrison, Robert W.²  Greaves, Graeme²  Knowles, Alexander J.¹  Smith, George D. W.³  Donnelly, Stephen E.²  Lee, William E.^1,4 

[1] Imperial Coll London, Dept Mat, Ctr Nucl Engn, London SW7 2BP, England

[2] Univ Huddersfield, Sch Comp & Engn, Huddersfield HD1 3DH, W Yorkshire, England

[3] Tokamak Energy Ltd, 120A Olymp Ave, Milton Pk OX1 4SA, Oxon, England

[4] Bangor Univ, Nucl Futures Inst, Bangor LL57 1UT, Gwynedd, Wales

关键词: Cermets;    Interface defects;    Irradiation;    Helium bubbles;    Transmission electron microscopy;   

DOI  :  10.1016/j.scriptamat.2018.06.027

来源: Elsevier

【 摘 要 】

A new candidate fusion engineering material, WC-FeCr, has been irradiated with He ions at 25 and 500 degrees C. Ions were injected at 6 keV to a dose of similar to 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 (similar to 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. (C) 2018 Acta Materialia Inc. Published by Elsevier Ltd.

【 授权许可】

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