Influence of Coating Thickness on High-temperature Steam Oxidation Kinetics and Mechanisms of Cr-coated Zr Alloy Cladding

被引:0
|
作者
Yan J. [1 ]
Gao S. [1 ]
Yang Z. [1 ]
Li S. [1 ]
Wang Z. [1 ]
Peng Z. [1 ]
Xue J. [1 ]
Liao Y. [1 ]
机构
[1] Institute for Nuclear Fuels and Materials, China Nuclear Power Technology Research Institute Co., Ltd., Guangdong, Shenzhen
来源
Surface Technology | 2024年 / 53卷 / 12期
关键词
coated Zr alloy cladding; coating thickness; high-temperature steam oxidation; oxidation kinetics; oxidation mechanism;
D O I
10.16490/j.cnki.issn.1001-3660.2024.12.012
中图分类号
学科分类号
摘要
Metal chromium is widely used as an antioxidant material because it is easy to develop a protective oxide scale in oxidizing environments. As a result, Cr has been extensively studied for use as a coating material for nuclear fuel cladding. The Cr-coated Zr alloy cladding is one of the most promising accident tolerant fuel (ATF) products for full engineering applications, due to its outstanding high-temperature steam oxidation resistance, satisfactory resistance to corrosion and fretting wear, and higher technological maturity and economic efficiency, less difficult engineering application. In this work, a Zr alloy cladding with outer diameter of 9.5 mm and wall thickness of 0.57 mm was used as the substrate to prepare Cr coatings by magnetron sputtering techniques. The target thickness of Cr coatings was set to 10, 15, and 20 μm with well control of thickness variations along the Zr alloy tube axis. High-temperature steam oxidation tests were conducted by synchronous thermogravimetric analyzer at 1 200 ℃ for oxidation time ranging from 500 s up to 3 000 s. The work aims to systematically study the effect of Cr coating thickness on the oxidation behavior, oxidation kinetics and microscopic mechanisms under hypothetical loss of coolant accident conditions for nuclear reactor. The microstructural characteristics including oxide thickness, element distribution, and phase composition were analyzed by energy dispersive X-ray spectroscopy (EDS), field emission scanning electron microscopy (SEM), and X-ray diffraction (XRD). The oxidation kinetics of Cr coatings based on Cr2O3 oxide thickness were constructed, and the effects of Cr coating thickness on high-temperature oxidation and failure mechanisms were also explored. A three-layer structure (Cr2O3, Cr, Zr-Cr from outside to inside) was formed. Interdiffusion at the coating and substrate interface resulted in the formation of a continuous Zr-Cr layer on the order of micrometer in thickness. It was shown that the protective effect on the Zr substrate was limited at a coating thickness of 10 μm. The protectiveness of Cr2O3 oxide scale and residual Cr coatings were completely lost for 2 000 s, which the substrate was oxidized. At a coating thickness of 15 μm, in the first stage, the oxidation kinetic of coatings followed a parabolic law with protectiveness, and the oxidation rate constant was 0.038 04 μm2/s. In the second stage, the oxidation kinetics shifted, and the protectiveness of Cr2O3 oxide and residual Cr coatings degraded, owing to the redox reaction between Zr and Cr2O3 oxide, and the development of grain boundaries ZrO2 particles within the residual Cr coating. Nevertheless, the oxide scale and coatings after degradation during 2 000 and 3 000 s could still hinder the oxidation of the Zr substrate to a certain extent. At a coating thickness of 20 μm, the overall oxidation kinetic of coatings always obeyed the parabolic law without transformation, and the oxide scale and residual coating were protective, in which the oxidation rate constant was 0.049 62 μm2/s. The results of this study show that the Cr-coated Zr cladding with the thickness of 15 and 20 μm exhibits the most promising behavior with an improved resistance to high temperature steam oxidation. These experimental results could provide data support and theoretical basis for the optimal design of coatings for ATF cladding. © 2024 Chongqing Wujiu Periodicals Press. All rights reserved.
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页码:147 / 157and251
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共 26 条
  • [11] REBAK R B., Accident-Tolerant Fuels Cladding Concept: Coatings for Zirconium Alloys, Accident Tolerant Materials for Light Water Reactor Fuels, pp. 63-81, (2020)
  • [12] YEOM H, MAIER B, JOHNSON G, Et al., High Temperature Oxidation and Microstructural Evolution of Cold Spray Chromium Coatings on Zircaloy-4 in Steam Environments, Journal of Nuclear Materials, 526, (2019)
  • [13] BRACHET J C, IDARRAGA-TRUJILLO I, LE FLEM M, Et al., Early Studies on Cr-Coated Zircaloy-4 as Enhanced Accident Tolerant Nuclear Fuel Claddings for Light Water Reactors, Journal of Nuclear Materials, 517, pp. 268-285, (2019)
  • [14] BRACHET J C, ROUESNE E, RIBIS J, Et al., High Temperature Steam Oxidation of Chromium-Coated Zirconium-Based Alloys: Kinetics and Process, Corrosion Science, 167, (2020)
  • [15] BRACHET J C, LE SAUX M, BISCHOFF J, Et al., Evaluation of Equivalent Cladding Reacted Parameters of Cr-Coated Claddings Oxidized in Steam at 1 200 ℃ in Relation with Oxygen Diffusion/Partitioning and Post-Quench Ductility, Journal of Nuclear Materials, 533, (2020)
  • [16] FAZI A, ABOULFADL H, IYER A H S, Et al., Characterization of As-Deposited Cold Sprayed Cr-Coating on Optimized ZIRLO™ Claddings, Journal of Nuclear Materials, 549, (2021)
  • [17] FAZI A, STILLER K, ANDREN H O, Et al., Cold Sprayed Cr-Coating on Optimized ZIRLO™ Claddings: The Cr/Zr Interface and Its Microstructural and Chemical Evolution after Autoclave Corrosion Testing, Journal of Nuclear Materials, 560, (2022)
  • [18] PENG Z X, WANG Z W, YAN J, Et al., Effects of Cr Coating on Fretting Wear Behavior of Zr-1Nb Alloy Cladding, Rare Metal Materials and Engineering, 51, 9, pp. 3419-3426, (2022)
  • [19] DUAN Z G, CHEN P, ZHOU Y, Et al., Current Progress of Cr-Coated Zirconium Alloy Cladding for Accident Tolerant Fuel, Nuclear Techniques, 45, 3, pp. 3-14, (2022)
  • [20] REED B, WANG R, LU R Y, Et al., Autoclave Grid-to-Rod Fretting Wear Evaluation of a Candidate Cladding Coating for Accident-Tolerant Fuel, Wear, 466, (2021)