Compatibility of erbium oxide coating with liquid lithium-lead alloy and corrosion protection effect of iron layer

被引：20

作者：

Chikada, Takumi ^{[1
]}

Suzuki, Akihiro ^{[2
]}

Terai, Takayuki ^{[1
]}

Muroga, Takeo ^{[3
]}

Koch, Freimut ^{[4
]}

机构：

[1] Univ Tokyo, Sch Engn, Inst Engn Innovat, Tokyo, Japan

[2] Univ Tokyo, Sch Engn, Nucl Profess Sch, Tokai, Ibaraki, Japan

[3] Natl Inst Fus Sci, Dept Helical Plasma Res, Toki, Gifu, Japan

[4] Max Planck Inst Plasma Phys, Garching, Germany

来源：

FUSION ENGINEERING AND DESIGN | 2013年 / 88卷 / 6-8期

关键词：

Lithium-lead; Tritium permeation; Corrosion; Coating; Erbium oxide; TRITIUM PERMEATION BARRIERS; ARC; FILMS;

D O I：

10.1016/j.fusengdes.2013.03.075

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：

Li-Pb compatibility of Er2O3 and Er2O3-Fe two-layer coatings has been explored for an understanding of corrosion behaviors and effects of the protection layer. The coatings wee peeled off after static Li-Pb immersion test at 600 degrees C due to the degradation of adhesion between the coating-substrate interface. A loss of Er and then subsequent corrosion of Er2O3 were shown after immersion at 500 degrees C for 500 and 1505 h. However, the outer Fe layer played a role to decrease corrosion rate of the coatings by comparing with the results of Er2O3 single layer coatings. Deuterium permeation measurements after corrosion tests at 500 degrees C showed that the Er2O3 coatings kept permeation reduction factors of 10(2)-10(3) after 500 h immersion, but seriously degraded after 1505 h immersion. Corrosion mechanisms suggest that corrosion protection properties will be modified by an optimization of the outer Fe layer and a control of oxygen concentration in Li-Pb. (C) 2013 Elsevier B.V. All rights reserved.

引用

页码：640 / 643

页数：4

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