Corrosion Behavior of Zr(Nb, Fe)2 Phase of Zr-Fe-Nb Alloy in 400℃/10.3 MPa Superheated Steam

被引：0
作者：
Lian A. [1 ]
Ma S. [1 ]
Li Q. [1 ]
Peng J. [1 ]
Liang X. [1 ]
Wang J. [1 ]
Yao M. [1 ]
机构：
[1] Laboratory for Microstructures, Shanghai University, Shanghai
来源：
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2019年 / 53卷 / 03期
关键词：
Crystal structure; Microstructure; Second phase particle; Zirconium alloy;
D O I：
10.7538/yzk.2018.youxian.0772
中图分类号：
学科分类号：
摘要：
The corrosion behavior for Zr-1.0Fe-1.0Nb specimens heat-treated at 580℃ for 5 h after β-quenching and cold rolling was investigated in 400℃/10.3 MPa superheated steam by autoclave tests. HRTEM and SEM equipped with EDS were employed to investigate the matrix microstructure and the oxidation behavior of the Zr(Nb, Fe)2 second phase particles (SPPs). Results show that the major SPPs are o-Zr3Fe and hcp-Zr(Nb, Fe)2. During the oxidation, Zr(Nb, Fe)2 SPPs are first oxidized into amorphous oxides and the amorphous oxides will be further oxidized into m-Nb2O5 and m-Fe2O3 phase nanocrystalline oxides, and finally the oxides are dissolved into the corrosive medium. The oxidation of Zr(Nb, Fe)2 is accompanied by the diffusion and loss of Fe and Nb elements with the loss rate of Nb larger than that of Fe, which contributes to large amount of defects within the oxidation layer and promotes the oxidation layer transition from columnar to equiaxed grains, deteriorating the corrosion resistance of the alloy. © 2019, Editorial Board of Atomic Energy Science and Technology. All right reserved.
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页码：420 / 426
页数：6
相关论文
共 17 条
  • [1] Kim H.G., Sang Y.P., Lee M.H., Et al., Corrosion and microstructural characteristics of Zr-Nb alloys with different Nb contents, Journal of Nuclear Materials, 373, 1, pp. 429-432, (2008)
  • [2] Kruger R.M., Adamson R.B., Brenner S.S., Effects of microchemistry and precipitate size on nodular corrosion resistance of Zircaloy-2, Journal of Nuclear Materials, 189, pp. 193-200, (1992)
  • [3] Zhou B., The problems of nodular corrosion in zircaloy, Chinese Journal of Nuclear Science and Engineering, 13, 1, pp. 51-58, (1993)
  • [4] Rudling P., Wikmark G., Lehtinen B., Et al., Impact of second phase particles on BWR Zr-2 corrosion and hydriding performance, Zirconium in the Nuclear Industry, Twelfth Symposium, pp. 678-770, (2000)
  • [5] Comstock R.J., Schoenberger G., Sabol G.P., Influence of processing variables and alloy chemistry on the corrosion behavior of ZIRLO nuclear fuel cladding, Zirconium in the Nuclear Industry, 11th Symposium, pp. 710-725, (1996)
  • [6] Nikulina A.V., Markelov V.A., Peregud M.M., Et al., Irradiation-induced microstructural changes in Zr-l%Sn-l%Nb-0.4%Fe, Journal of Nuclear Materials, 238, pp. 205-210, (1996)
  • [7] Shishov V.N., Peregud M.M., Nikulina A.V., Et al., Influence of structure-phase state of Nb containing Zr alloys irradiation-induced growth, Zirconium in the Nuclear Industry, 14th Symposium, pp. 666-685, (2005)
  • [8] Dai X., Wang P., Wang Y., Et al., Study on second phase particles in N36 alloy claddings and bars, Nuclear Power Engineering, 38, pp. 13-17, (2017)
  • [9] Li Z., Zhou L., Zhang J., Et al., The existing form of Nb in Zr-Sn-Nb-Fe alloys and its dependence on intermediate annealing, Rare Metal Materials and Engineering, 33, 12, pp. 362-364, (2004)
  • [10] Kim H.G., Park J.Y., Jeong Y.H., Ex-reactor corrosion and oxide characteristics of Zr-Nb-Fe alloys with the Nb/Fe ratio, Journal of Nuclear Materials, 345, 1, pp. 1-10, (2005)
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