Oxidation behavior and kinetics of magnetron-sputtered Cr-coated Zr alloy cladding in 1000-1300 °C steam environment

被引:32
作者
Wang, Dong [1 ]
Zhong, Ruhao [2 ]
Zhang, Yapei [1 ]
Chen, Peng [2 ]
Yu, Jian [1 ]
Lan, Yicong [1 ]
Qiu, Suizheng [1 ]
Tian, Wenxi [1 ]
Liao, Yehong [2 ]
Peng, Zhenxun [2 ]
机构
[1] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Shaanxi Key Lab Adv Nucl Energy & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R China
[2] China Nucl Power Technol Res Inst, Shenzhen 518000, Peoples R China
基金
国家重点研发计划;
关键词
Accident tolerant fuel (ATF); Cr coating; Zr alloy cladding; High temperature steam oxidation; Oxidation kinetics; HIGH-TEMPERATURE OXIDATION; ACCIDENT; COATINGS; PERFORMANCE;
D O I
10.1016/j.corsci.2023.111215
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The isothermal oxidation behavior of magnetron-sputtered Cr-coated Zr-1Nb alloy cladding in 1000-1300 degrees C steam environment is studied. The phenomena at each temperature are summarized and the oxidation kinetics are discussed. Cr coating can maintain the oxidation resistance for more than 6 h at 1000 degrees C and 1100 degrees C under double-sided oxidation condition, while suffered degradation during long-duration oxidation at 1200 degrees C and 1300 degrees C. After coating degradation, Zr substrate was oxidized prior to residual metallic Cr and the metallic Cr was not completely oxidized until the ZrO2 layer beneath the coating had grown to a certain thickness. Mainly due to the redox reaction between Zr and Cr2O3 and the preferential oxidation of Zr substrate, the thickness of Cr2O3 film decreased after a certain oxidation duration. The Cr coating after degradation at 1200 degrees C can still hinder the oxidation of Zr substrate to a certain extent, while that at 1300 degrees C almost lost the protective effect.
引用
收藏
页数:15
相关论文
共 42 条
[1]   AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding [J].
Bischoff, Jeremy ;
Delafoy, Christine ;
Vauglin, Christine ;
Barberis, Pierre ;
Roubeyrie, Cedric ;
Perche, Delphine ;
Duthoo, Dominique ;
Schuster, Frederic ;
Brachet, Jean-Christophe ;
Schweitzer, Elmar W. ;
Nimishakavi, Kiran .
NUCLEAR ENGINEERING AND TECHNOLOGY, 2018, 50 (02) :223-228
[2]  
Brachet J.C., CORROS SCI, V167, P2020
[3]  
Brachet J.-C., 2017, WRFPM 2017 WATER REA
[4]  
Cathcart J.V., 1977, Zirconium Metal-Water Oxidation Kinetics IV, Reaction Rate Studies
[5]   Microstructure and high-temperature steam oxidation properties of thick Cr coatings prepared by magnetron sputtering for accident tolerant fuel claddings: The role of bias in the deposition process [J].
Chen, Q. S. ;
Liu, C. H. ;
Zhang, R. Q. ;
Yang, H. Y. ;
Wei, T. G. ;
Wang, Y. ;
Li, Z. ;
He, L. X. ;
Wang, J. ;
Wang, L. ;
Long, J. P. ;
Chang, H. .
CORROSION SCIENCE, 2020, 165
[6]   Design and characterization of zirconium-based multilayer coating for carbon/carbon composites against oxyacetylene ablation [J].
Feng, Guanghui ;
Chen, Lei ;
Yao, Xiyuan ;
Yu, Yulan ;
Li, Hejun .
CORROSION SCIENCE, 2021, 192
[7]   A systematic study of the oxidation behavior of Cr coatings on Zry4 substrates in high temperature steam environment [J].
Han, Xiaochun ;
Chen, Chen ;
Tan, Yongqiang ;
Feng, Wanlin ;
Peng, Shuming ;
Zhang, Haibin .
CORROSION SCIENCE, 2020, 174
[8]   An interesting oxidation phenomenon of Cr coatings on Zry-4 substrates in high temperature steam environment [J].
Han, Xiaochun ;
Xue, Jiaxiang ;
Peng, Shuming ;
Zhang, Haibin .
CORROSION SCIENCE, 2019, 156 :117-124
[9]   Role of water vapor in chromia-scale growth at low oxygen partial pressure [J].
Hänsel, M ;
Quadakkers, WJ ;
Young, DJ .
OXIDATION OF METALS, 2003, 59 (3-4) :285-301
[10]   Preliminary evaluation of U3Si2-FeCrAl fuel performance in light water reactors through a multi-physics coupled way [J].
He, Yanan ;
Chen, Ping ;
Wu, Yingwei ;
Su, G. H. ;
Tian, Wenxi ;
Qiu, Suizheng .
NUCLEAR ENGINEERING AND DESIGN, 2018, 328 :27-35