Corrosion tests of multi-layer ceramic coatings in liquid lithium-lead

被引:8
作者
Akahoshi, Erika [1 ]
Matsunaga, Moeki [1 ]
Kimura, Keisuke [1 ]
Nakamura, Kazuki [1 ]
Balden, Martin [2 ]
Hishinuma, Yoshimitsu [3 ]
Chikada, Takumi [1 ]
机构
[1] Shizuoka Univ, Shizuoka, Japan
[2] Max Planck Inst Plasma Phys, Garching, Germany
[3] Natl Inst Fus Sci, Gifu, Japan
关键词
Lithium-lead; Corrosion; Ceramic coating; Erbium oxide; Zirconium oxide; YTTRIUM-OXIDE; ERBIUM OXIDE;
D O I
10.1016/j.fusengdes.2020.111874
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
Tritium permeation through structural materials in fusion reactor blanket systems is a critical issue from the viewpoints of fuel loss and radiological safety. Ceramic coatings have been investigated to prevent tritium permeation; however, corrosion of the coatings by blanket materials, especially corrosive liquid tritium breeders such as lithium-lead is serious. In our previous study, the improvement of permeation reduction performance using an erbium oxide (Er2O3)-zirconium oxide (ZrO2) two-layer coating was confirmed, but it did not show substantial corrosion resistance. In this study, various mull-layer coatings were fabricated by metal organic decomposition and then exposed to lithium-lead under static conditions to investigate precise corrosion behaviors of mull-layer coatings. After lithium-lead exposure for 1000 h at 600 degrees C, the outermost Er2O3 layer almost disappeared, while the outermost ZrO2 layer remained, indicating that ZrO2 is more suitable as the outermost layer. However, many cracks and peelings were observed on the outermost ZrO2 layer in the cases of the samples having four coating interfaces. The optimization of layer combination and the control of adhesion between the coatings are required to reduce the degradation of mull-layer coatings.
引用
收藏
页数:5
相关论文
共 10 条
[1]   Surface behaviour in deuterium permeation through erbium oxide coatings [J].
Chikada, T. ;
Suzuki, A. ;
Adelhelm, C. ;
Terai, T. ;
Muroga, T. .
NUCLEAR FUSION, 2011, 51 (06)
[2]   Fabrication technology development and characterization of tritium permeation barriers by a liquid phase method [J].
Chikada, Takumi ;
Matsunaga, Moeki ;
Horikoshi, Seira ;
Mochizuki, Jumpei ;
Fujita, Hikari ;
Hishinuma, Yoshimitsu ;
Isobe, Kanetsugu ;
Hayashi, Takumi ;
Terai, Takayuki ;
Oya, Yasuhisa .
FUSION ENGINEERING AND DESIGN, 2018, 136 :215-218
[3]   Crystallization and deuterium permeation behaviors of yttrium oxide coating prepared by metal organic decomposition [J].
Chikada, Takumi ;
Tanaka, Teruya ;
Yuyama, Kenta ;
Uemura, Yuki ;
Sakurada, Shodai ;
Fujita, Hiroe ;
Li, Xiao-Chun ;
Isobe, Kanetsugu ;
Hayashi, Takumi ;
Oya, Yasuhisa .
NUCLEAR MATERIALS AND ENERGY, 2016, 9 :529-534
[4]   Microstructure control and deuterium permeability of erbium oxide coating on ferritic/martensitic steels by metal-organic decomposition [J].
Chikada, Takumi ;
Suzuki, Akihiro ;
Tanaka, Teruya ;
Terai, Takayuki ;
Muroga, Takeo .
FUSION ENGINEERING AND DESIGN, 2010, 85 (7-9) :1537-1541
[5]   Development of advanced high heat flux and plasma-facing materials [J].
Linsmeier, Ch. ;
Rieth, M. ;
Aktaa, J. ;
Chikada, T. ;
Hoffmann, A. ;
Hoffmann, J. ;
Houben, A. ;
Kurishita, H. ;
Jin, X. ;
Li, M. ;
Litnovsky, A. ;
Matsuo, S. ;
von Mueller, A. ;
Nikolic, V. ;
Palacios, T. ;
Pippan, R. ;
Qu, D. ;
Reiser, J. ;
Riesch, J. ;
Shikama, T. ;
Stieglitz, R. ;
Weber, T. ;
Wurster, S. ;
You, J. -H. ;
Zhou, Z. .
NUCLEAR FUSION, 2017, 57 (09)
[6]   Lithium-lead corrosion behavior of erbium oxide, yttrium oxide and zirconium oxide coatings fabricated by metal organic decomposition [J].
Matsunaga, Moeki ;
Horikoshi, Seira ;
Mochizuki, Jumpei ;
Fujita, Hikari ;
Hishinuma, Yoshimitsu ;
Isobe, Kanetsugu ;
Hayashi, Takumi ;
Terai, Takayuki ;
Oya, Yasuhisa ;
Chikada, Takumi .
JOURNAL OF NUCLEAR MATERIALS, 2018, 511 :537-543
[7]   Preparation and characterization of Er2O3-ZrO2 multi-layer coating for tritium permeation barrier by metal organic decomposition [J].
Mochizuki, Jumpei ;
Horikoshi, Seira ;
Fujita, Hikari ;
Matsunaga, Moeki ;
Hishinuma, Yoshimitsu ;
Oya, Yasuhisa ;
Chikada, Takumi .
FUSION ENGINEERING AND DESIGN, 2018, 136 :219-222
[8]   LiErO2 formation on Er2O3 in static and natural convection lithium [J].
Nagura, Masaru ;
Suzuki, Akihiro ;
Muroga, Takeo ;
Terai, Takayuki .
FUSION ENGINEERING AND DESIGN, 2009, 84 (7-11) :1384-1387
[9]   Effect of film thickness on the stress and adhesion of diamond-like carbon coatings [J].
Sheeja, D ;
Tay, BK ;
Leong, KW ;
Lee, CH .
DIAMOND AND RELATED MATERIALS, 2002, 11 (09) :1643-1647
[10]   Control of substrate oxidation in MOD ceramic coating on low-activation ferritic steel with reduced-pressure atmosphere [J].
Tanaka, Teruya ;
Muroga, Takeo .
JOURNAL OF NUCLEAR MATERIALS, 2014, 455 (1-3) :630-634