Journal
FUSION ENGINEERING AND DESIGN
Volume 124, Issue -, Pages 1118-1121Publisher
ELSEVIER SCIENCE SA
DOI: 10.1016/j.fusengdes.2017.03.001
Keywords
Tungsten; Self-passivating alloy; Oxidation behavior; Yttrium; Thermo-shock
Categories
Funding
- Euratom research and training programme [633053]
- Basque Government [ELKARTEK FRONTIERS KK-2015/00101]
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The use of self-passivating tungsten alloys for the first wall armor of future fusion reactors is advantageous concerning safety issues in comparison with pure tungsten. Bulk W-10Cr-0.5Y alloy manufactured by mechanical alloying followed by HIP resulted in a fully dense material with grain size around 100 nm and a dispersion of Y-rich oxide nanoparticles located at the grain boundaries. An improvement in flexural strength and fracture toughness was observed with respect to previous works. Oxidation tests under isothermal and accident-like conditions revealed a very promising oxidation behavior for the W-10Cr-0.5Y alloy. Thermo-shock tests at JUDITH-1 to simulate ELM-like loads resulted in a crack network at the surface with roughness values lower than those of a pure W reference material. An additional thermal treatment at 1550 degrees C improves slightly the oxidation and significantly thermo-shock resistance of the alloy. (C) 2017 The Authors. Published by Elsevier B.V.
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