Self-passivating W-Cr-Y alloys: Characterization and testing

被引：34

作者：

Calvo, Aida ^{[1
,2
]}

Garcla-Rosales, Carmen ^{[1
,2
]}

Ordas, Nerea ^{[1
,2
]}

Iturriza, Inigo ^{[1
,2
]}

Schlueter, Karsten ^{[3
]}

Koch, Freimut ^{[3
]}

Pintsuk, Gerald ^{[4
]}

Tejado, Elena ^{[5
]}

Ygnacio Pastor, Jose ^{[5
]}

机构：

[1] Univ Navarra, Ceit IK4, E-20018 San Sebastian, Spain

[2] Univ Navarra, TECNUN, E-20018 San Sebastian, Spain

[3] Max Planck Inst Plasma Phys, D-85748 Garching, Germany

[4] Forschungszentrum Julich, D-52425 Julich, Germany

[5] Univ Politecn Madrid, E-28040 Madrid, Spain

来源：

FUSION ENGINEERING AND DESIGN | 2017年 / 124卷

关键词：

Tungsten; Self-passivating alloy; Oxidation behavior; Yttrium; Thermo-shock; OXIDATION BEHAVIOR; TUNGSTEN ALLOYS; MICROSTRUCTURE;

D O I：

10.1016/j.fusengdes.2017.03.001

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

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.

引用

页码：1118 / 1121

页数：4

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