Temperature-time dependence and mechanisms of redox reaction in Cr-coated Zr alloy cladding during steam oxidation at 900-1250 °C

被引:8
作者
Deng, Jianxi [1 ]
Zuo, Jiadong [1 ]
Geng, Donghui [1 ]
Sun, Qiaoyan [1 ]
Song, Zhongxiao [1 ]
Sun, Jun [1 ]
机构
[1] Xi An Jiao Tong Univ, State Key Lab Mech Behav Mat, Xian 710049, Shaanxi, Peoples R China
基金
中国国家自然科学基金;
关键词
Cr-coated Zr alloy cladding; High temperature steam oxidation; Layered structures; Diffusion behavior; Redox reaction mechanism; ACCIDENT-TOLERANT FUELS; BEHAVIOR;
D O I
10.1016/j.jnucmat.2024.155094
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The structural integrity of the Cr coating can be significantly affected with increasing temperature during steam oxidation. Herein, the elemental diffusion, layered structure, and kinetics evolution of Cr coating in steam environment of 900-1250 degrees C for 0.5 to 3 h were studied. The oxidation behavior of Cr-coated Zr claddings associated with redox reaction between Cr2O3 and Zr were investigated in detail. Cr2O3 layer forms on Cr coating for steam oxidation at 900 degrees C and Cr-Zr diffusion layer appears at interface between Cr coating and Zr substrate when the samples are subjected to steam oxidation at 1000-1150 degrees C for 3 h. The starting time for redox reaction decreases dramatically when the temperature is higher than 1150 degrees C. A prediction modal based on Fick's Law was put forward to predict the starting time of redox reaction for 1100 to 1250 degrees C. The prediction is consistent with the experimental results. Furthermore, the initial process of redox reaction was investigated and analyzed in detail. Predominated by ion transportation within residual Cr layer, O2- from Cr2O3 could diffuse along the ZrO2 particles at Cr coating boundaries to the Cr-Zr layer, resulting in the reduction of Cr2O3 and partial oxidation of diffusion layer.
引用
收藏
页数:13
相关论文
共 38 条
[1]  
Arias D., 1986, Bull. Alloy Phase Diagr, V7, P237, DOI [10.1007/BF02868997, DOI 10.1007/BF02868997]
[2]  
Baker Louis, 1962, ANL-6548, DOI [10.2172/4781681, DOI 10.2172/4781681]
[3]   Irradiation with hydrogen atoms and ions as an accelerated hydrogenation test of zirconium alloys and protective coatings [J].
Begrambekou, L. B. ;
Evsin, A. E. ;
Grunin, A. V. ;
Gumarov, A. I. ;
Kaplevsky, A. S. ;
Kashapov, N. F. ;
Luchkin, A. G. ;
Vakhitov, I. R. ;
Yanilkin, I. V. ;
Tagirov, L. R. .
INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, 2019, 44 (31) :17154-17162
[4]  
Brachet J.C., 2015, FONT 8 CONTR MAT INV
[5]   High temperature steam oxidation of chromium-coated zirconium-based alloys: Kinetics and process [J].
Brachet, Jean-Christophe ;
Rouesne, Elodie ;
Ribis, Joel ;
Guilbert, Thomas ;
Urvoy, Stephane ;
Nony, Guillaume ;
Toffolon-Masclet, Caroline ;
Le Saux, Matthieu ;
Chaabane, Nihed ;
Palancher, Herve ;
David, Amandine ;
Bischoff, Jeremy ;
Augereau, Julien ;
Pouillier, Edouard .
CORROSION SCIENCE, 2020, 167
[6]   Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors [J].
Brachet, Jean-Christophe ;
Idarraga-Trujillo, Isabel ;
Le Flem, Marion ;
Le Saux, Matthieu ;
Vandenberghe, Valerie ;
Urvoy, Stephane ;
Rouesne, Elodie ;
Guilbert, Thomas ;
Toffolon-Masclet, Caroline ;
Tupin, Marc ;
Phalippou, Christian ;
Lomello, Fernando ;
Schuster, Frederic ;
Billard, Alain ;
Velisa, Gihan ;
Ducros, Cedric ;
Sanchette, Frederic .
JOURNAL OF NUCLEAR MATERIALS, 2019, 517 :268-285
[7]  
Cathcart J.V., 1977, ORNL/NUREG-17, DOI [https://doi.org/10.2172/7317596, DOI 10.2172/7317596]
[8]  
Chase M. W., 1998, NIST-JANAF Thermochemical Tables
[9]   Steam oxidation of Cr-coated zirconium alloy claddings at 1200 °C: Kinetics transition and failure mechanism of Cr coatings [J].
Deng, Jianxi ;
Geng, Donghui ;
Sun, Qiaoyan ;
Song, Zhongxiao ;
Sun, Jun .
JOURNAL OF NUCLEAR MATERIALS, 2023, 586
[10]  
Goldner F., 2012, NUCL EN ADV COMM M W