Corrosion behavior of Cr-coated zirconium alloy cladding in LiOH/H3BO3-containing water at 360 °C

被引：10
作者：
Ma, Haibin [1 ]
Zhang, Honglin [2 ]
Hu, Lijuan [2 ]
Li, Sigong [1 ]
Zhang, Jianan [2 ]
Zhang, Wenhuai [2 ]
Sun, Rongrong [2 ]
Yao, Meiyi [2 ]
Xue, Jiaxiang [1 ]
Ren, Qisen [1 ]
Liao, Yehong [1 ]
机构：
[1] China Nucl Power Technol Res Inst, Nucl Fuel & Mat Dept, Shenzhen 518026, Peoples R China
[2] Shanghai Univ, Inst Mat, Sch Mat Sci & Engn, Shanghai 200072, Peoples R China
来源：
CORROSION SCIENCE | 2023年 / 222卷
基金：
中国国家自然科学基金;
关键词：
ATF cladding material; Zirconium alloy; Cr coating; Corrosion behavior; POTENTIAL-PH DIAGRAMS; ACCIDENT; OXIDATION; COATINGS; CHROMIUM;
D O I：
10.1016/j.corsci.2023.111386
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The corrosion behaviors of Cr-coated zirconium alloy (Zr-0.9 Nb) tube were investigated in 70 ppm Li and 3.5 ppm Li+ 1000 ppm B aqueous solutions at 360 degrees C/18.6 MPa by static autoclave tests, respectively. Results show that Cr coating improves the corrosion resistance of Zr-0.9 Nb under LiOH and Li+B conditions. The corrosion products of Cr coating were Cr2O3 and Cr(OH)3, while the Cr2O3 was more easily transformed into Cr(OH)3 under LiOH conditions. Some of the Cr(OH)3 dissolved in the late stage of corrosion, resulting in the thinning of the oxide film. Data availability: The raw/processed data required to reproduce these findings cannot be shared at this time due to technical or time limitations.
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页数：8
相关论文
共 31 条
  • [1] BISCHOF J, 2016, LIQUIDITY ENFORCEMEN, P1
  • [2] AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding
    Bischoff, Jeremy
    Delafoy, Christine
    Vauglin, Christine
    Barberis, Pierre
    Roubeyrie, Cedric
    Perche, Delphine
    Duthoo, Dominique
    Schuster, Frederic
    Brachet, Jean-Christophe
    Schweitzer, Elmar W.
    Nimishakavi, Kiran
    [J]. NUCLEAR ENGINEERING AND TECHNOLOGY, 2018, 50 (02) : 223 - 228
  • [3] High temperature steam oxidation of chromium-coated zirconium-based alloys: Kinetics and process
    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
    [J]. CORROSION SCIENCE, 2020, 167
  • [4] Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors
    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
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2019, 517 : 268 - 285
  • [5] Recent studies on potential accident-tolerant fuel-cladding systems in light water reactors
    Chen, Sheng-Li
    He, Xiu-Jie
    Yuan, Cen-Xi
    [J]. NUCLEAR SCIENCE AND TECHNIQUES, 2020, 31 (03)
  • [6] Cheng J., 2002, P CSEE, V22
  • [7] Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding
    Dryepondt, Sebastien
    Unocic, Kinga A.
    Hoelzer, David T.
    Massey, Caleb P.
    Pint, Bruce A.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2018, 501 : 59 - 71
  • [8] Mechanical behavior of a chromium coating on a zirconium alloy substrate at room temperature
    Duc Vinh Nguyen
    Le Saux, Matthieu
    Gelebart, Lionel
    Brachet, Jean-Christophe
    Bonthonneau, Jean-Philippe
    Courcelle, Arnaud
    Guillou, Raphaelle
    Rouesne, Elodie
    Urvoy, Stephane
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2022, 558
  • [9] Cold sprayed Cr-coating on Optimized ZIRLO™ claddings: the Cr/Zr interface and its microstructural and chemical evolution after autoclave corrosion testing
    Fazi, Andrea
    Stiller, Krystyna
    Andren, Hans-Olof
    Thuvander, Mattias
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2022, 560
  • [10] High-temperature oxidation of thick Cr coating prepared by arc deposition for accident tolerant fuel claddings
    Hu, Xiaogang
    Dong, Chuang
    Wang, Qing
    Chen, Baoqing
    Yang, Hongyan
    Wei, Tianguo
    Zhang, Ruiqian
    Gu, Wei
    Chen, Damin
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2019, 519 : 145 - 156
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