Design and properties of FeAl/Al2O3/TiO2 composite tritium-resistant coating prepared through pack cementation and sol-gel method

被引：12
作者：
Zhu, Liu [1 ]
Zheng, Liang [2 ]
Xie, Hao [3 ]
Liu, Dong-Guang [2 ]
Xu, Qiu [4 ]
Luo, Lai-Ma [3 ,5 ]
Wu, Yu-Cheng [3 ,5 ]
机构：
[1] Taizhou Univ, Sch Pharmaceut & Mat Engn, Taizhou 318000, Peoples R China
[2] Hefei Univ Technol, Ind & Equipment Technol, Hefei 230009, Peoples R China
[3] Hefei Univ Technol, Sch Mat Sci & Engn, Hefei 230009, Peoples R China
[4] Kyoto Univ, Inst Integrated Radiat & Nucl Sci, Osaka 5900494, Japan
[5] Natl Local Joint Engn Res Ctr Nonferrous Met & Pr, Hefei 230009, Peoples R China
来源：
MATERIALS TODAY COMMUNICATIONS | 2021年 / 26卷
基金：
中国国家自然科学基金;
关键词：
Tritiumpermeation barrier; FeAl/Al2O3/TiO2 composite coating; Pack cementation; Sol-gel; Microstructure; Bonding strength;
D O I：
10.1016/j.mtcomm.2020.101848
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
Structural steel materials exist in tritium breeding blankets and auxiliary tritium handling systems in fusion reactors. Applying a tritium permeation barrier coating on the surface of the structural material is necessary to prevent material corrosion and embrittlement. In this study, FeAl/Al2O3/TiO2 composite tritium-resistant coating on 316 L stainless steel substrate was successfully prepared by pack cementation and sol-gel method. The surface and cross-section morphologies of the composite coatings were systematically studied. The hydrogen permeation properties and adhesion between the different composite coatings were investigated. Results show that the FeAl/Al2O3/TiO2 composite tritium resistant coating is uniform, dense, and preferably connected to the substrate without defects such as cracks and pores. Compared with FeAl/Al2O3 coating, FeAl/Al2O3/TiO2 coating has better bonding strength, toughness, and ductility. Hydrogen permeation test shows that the design of the FeAl/Al2O3/TiO2 composite coating improves the hydrogen resistance of the coating at room temperature.
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页数：9
相关论文
共 56 条
[1]   An overview on tritium permeation barrier development for WCLL blanket concept [J].
Aiello, A ;
Ciampichetti, A ;
Benamati, G .
JOURNAL OF NUCLEAR MATERIALS, 2004, 329 :1398-1402
[2]   Electrochemical method for measuring hydrogen permeability through metals [J].
Akamatsu, T ;
Kume, Y ;
Komiya, K ;
Yukawa, H ;
Morinaga, M ;
Yamaguchi, S .
JOURNAL OF ALLOYS AND COMPOUNDS, 2005, 393 (1-2) :302-306
[3]   Formation and oxidation performance of low-temperature pack aluminide coatings on ferritic-martensitic steels [J].
Bates, B. L. ;
Wang, Y. Q. ;
Zhang, Y. ;
Pint, B. A. .
SURFACE & COATINGS TECHNOLOGY, 2009, 204 (6-7) :766-770
[4]   Sintering of α-Al2O3 nanocrystalline ceramic from large α-Al2O3 polycrystalline nanoparticles [J].
Cao, Wenbin ;
Mao, Xuan ;
Li, Lu ;
Wang, Bing ;
Guo, Qian ;
Li, Jiangong .
CERAMICS INTERNATIONAL, 2017, 43 (01) :1378-1382
[5]  
Causey RA, 2012, COMPREHENSIVE NUCLEAR MATERIALS, VOL 4: RADIATION EFFECTS IN STRUCTURAL AND FUNCTIONAL MATERIALS FOR FISSION AND FUSION REACTORS, P511
[6]   THE USE OF SILICON-CARBIDE AS A TRITIUM PERMEATION BARRIER [J].
CAUSEY, RA ;
WAMPLER, WR .
JOURNAL OF NUCLEAR MATERIALS, 1995, 220 :823-826
[7]   Growth of inter-metallic compound layers on CLAM steel by HDA and preparation of permeation barrier by oxidation [J].
Chen, Jun ;
Li, Xianfen ;
Hua, Peng ;
Wang, Chunyan ;
Chen, Ke ;
Wu, Yucheng ;
Zhou, Wei .
FUSION ENGINEERING AND DESIGN, 2017, 125 :57-63
[8]   Deuterium permeation through erbium oxide coatings on RAFM steels by a dip-coating technique [J].
Chikada, Takumi ;
Naitoh, Shunya ;
Suzuki, Akihiro ;
Terai, Takayuki ;
Tanaka, Teruya ;
Muroga, Takeo .
JOURNAL OF NUCLEAR MATERIALS, 2013, 442 (1-3) :533-537
[9]   Deuterium permeation and thermal behaviors of amorphous silicon carbide coatings on steels [J].
Chikada, Takumi ;
Suzuki, Akihiro ;
Terai, Takayuki .
FUSION ENGINEERING AND DESIGN, 2011, 86 (9-11) :2192-2195
[10]   Tritium inventories and tritium safety design principles for the fuel cycle of ITER [J].
Cristescu, I. R. ;
Cristescu, I. ;
Doerri, L. ;
Glugla, M. ;
Murdoch, D. .
NUCLEAR FUSION, 2007, 47 (07) :S458-S463
123456