Behavior of plasma sprayed Cr coatings and FeCrAl coatings on Zr fuel cladding under loss-of-coolant accident conditions

被引:107
作者
Wang, Yiding [1 ]
Zhou, Wancheng [1 ]
Wen, Qinlong [1 ]
Ruan, Xingcui [1 ]
Luo, Fa [1 ]
Bai, Guanghai [2 ]
Qing, Yuchang [1 ]
Zhu, Dongmei [1 ]
Huang, Zhibin [1 ]
Zhang, Yanwei [2 ]
Li, Tong [3 ]
Li, Rui [3 ]
机构
[1] Northwestern Polytech Univ, State Key Lab Solidificat Proc, Sch Mat Sci & Engn, Xian 710072, Shaanxi, Peoples R China
[2] Suzhou Nucl Power Res Inst, Suzhou 215004, Peoples R China
[3] China Nucl Power Technol Res Inst, Shenzhen 518026, Peoples R China
基金
中国国家自然科学基金;
关键词
Accident tolerance fuel cladding; Plasma spraying; Cr coatings; FeCrAl coatings; Loss-of-coolant accident; HIGH-TEMPERATURE OXIDATION; SILICON-CARBIDE; ALLOYS; STEAM; IRON; ENVIRONMENTS; CHROMIUM;
D O I
10.1016/j.surfcoat.2018.03.016
中图分类号
TB3 [工程材料学];
学科分类号
0805 ; 080502 ;
摘要
To fabricate the oxidation resistance accident tolerance fuel cladding, Cr layer and FeCrAl alloys were deposited on Zircaloy-4 using atmospheric plasma spraying technology. The specimens were exposed under a simulated loss-of-coolant accident condition. XRD, SEM and EDS techniques were carried out to explore their high temperature behavior. According to the analysis results, both Cr coating and FeCrAl coating were successfully prepared by atmospheric plasma spraying system. Cr coating had superior oxidation resistance. Compact Cr2O3 scale forming on Cr coating acted as an oxygen diffusion barrier, whereas FeCrAl coating degraded due to inter-diffusion, leading to its poor protection for the cladding. Difference in standard Gibbs free energy of formation of Fe and Zr caused the prior oxidation of Zr. Accordingly, Zr-rich and Zr-depleted zones occurred in FeCrAl-coated specimens.
引用
收藏
页码:141 / 148
页数:8
相关论文
共 30 条
[1]  
[Anonymous], 2004, THERMAL SPRAY TECHNO
[2]   Selection of fuel cladding material for nuclear fission reactors [J].
Azevedo, C. R. F. .
ENGINEERING FAILURE ANALYSIS, 2011, 18 (08) :1943-1962
[3]  
Birks N, 2006, INTRODUCTION TO THE HIGH-TEMPERATURE OXIDATION OF METALS, 2ND EDITION, P1, DOI 10.1017/CBO9781139163903
[4]   Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding [J].
Cheng, Bo ;
Kim, Young-Jin ;
Chou, Peter .
NUCLEAR ENGINEERING AND TECHNOLOGY, 2016, 48 (01) :16-25
[5]   OXIDATION/VAPORIZATION KINETICS OF CR2O3 [J].
GRAHAM, HC ;
DAVIS, HH .
JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1971, 54 (02) :89-&
[6]   Cladding for high performance fuel [J].
Hallstadius, Lars ;
Johnson, Steven ;
Lahoda, Ed .
PROGRESS IN NUCLEAR ENERGY, 2012, 57 :71-76
[7]  
Haynes W.M., 2016, CRC Handbook of Chemistry and Physics: A Ready-Reference Book of Chemical and Physical Data, V97th, p2016th
[8]  
Kim H.-G., 2013, HIGH TEMPERATURE OXI
[9]   Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating [J].
Kim, Hyun-Gil ;
Kim, Il-Hyun ;
Jung, Yang-Il ;
Park, Dong-Jun ;
Park, Jeong-Yong ;
Koo, Yang-Hyun .
JOURNAL OF NUCLEAR MATERIALS, 2015, 465 :531-539
[10]   XPS/GIXS studies of thin oxide films formed on Fe-Cr alloys [J].
Kosaka, T ;
Suzuki, S ;
Inoue, H ;
Saito, M ;
Waseda, Y ;
Matsubara, E .
APPLIED SURFACE SCIENCE, 1996, 103 (01) :55-61