Journal of Nuclear Science, Engineering and Technology (JONSAT)
In cooperation with the Iranian Nuclear Society

Effect of Pickling and Anodizing on Corrosion Behavior of VVER fuel Clads

Document Type : Research Paper

Authors

Mahdi Dadfar
M Ansaripour
A Heidarpour
Z Arasteh
https://doi.org/10.24200/nst.2019.229
Abstract
Recently, it has been declared that fuel rods do not need to be anodized for the usage in VVER reactors. In this regard, some studies were planned to investigate the effects of pickling and anodizing treatments on corrosion behaviour of the fuel clads produced by Sooreh company. For this reason, different surface treated samples of as-received, grinded, pickled, grinded and anodized, and pickled and anodized were prepared. The Russian fuel clads in some equal conditions were also employed for comparisons. The results revealed that corrosion behaviour is completely effected by the surface treatment, and microstructure properties have less impact. The oxidation type in the pickled, and pickled and anodized samples are absolutely different from the grinded samples. The anodizing treatment after pickling nearly increases the corrosion resistance by two times in comparison to just pickled ones. The presence of grey oxide layer on the grinded samples are attributed to Monoclinic zirconia which has less corrosion resistance to Tetragonal zirconia.

Highlights

 [1] T.R. Allen, R.J.M. Konings, A.T. Motta, Corrosion of Zirconium Alloys, Comprehensive Nuclear Materials, Oxford: Elsevier, (2012) 49-68.

 [2] ASM Handbook, Surface engineering, 5, Surface Cleaning, Finishing, and Coating (1996).

 [3] J.S. Forster, P.S. Philli, T.K. Di Alexander, R.L. Tapping, T. Laursen, J.R. Leslie, The effect of anodic oxidation on near-surface deuterium in Zr-2.5 wt.% Nb. Nuclear Instruments and ethods in Physics Research Section B: Beam Interactions with Materials and Atoms, 48(1-4) (1990) 4.

 [4] G.A. McRae, M.A. Maguire, C.A. Jeffrey, D.A. Guzonas, C.A. Brown, A comparison of fractal dimensions determined from atomic force microscopy and impedance spectroscopy of anodic oxides on Zr–2.5Nb, Applied Surface Science, 191(1-4) (2002) 10.

 [5] F. Rosalbino, D. Maccio, A. Saccone, E. Angelini, Effect of Nb alloying additions on the characteristics of anodic oxide films on zirconium and their stability in NaOH solution, Journal of Solid State Electrochemistry, 14(8) (2010) 5.

 [6] A. Nikulina, S. Shishov, B. Cox, F. Garzalli, P. Rudling, Manufacturing of Zr-Nb Alloys, ZIRAT-special topic report (2006). 

[7] International Atomic Energy Agency, Waterside corrosion of zirconium alloys in nuclear power plants, IAEA-TECDOC-996, Vienna January (1998).

 [8] J. Godlewski, J.P. Gross, M. Lambertin, M. Wadier, J.F. Weidinger, Proceedings of 9th International Symposium on Zirconium in the Nuclear Industry, ASTM-STP, 1132 (1991) 416.

 [9] D. Pecheur, J. Godlewski, J. Peybernes, L. Fayette, M. Noe, A. Frichet, O. Kerrec, Proceedings of 12th International Symposium on Zirconium in the Nuclear Industry, ASTM STP, 1354 (1998) 793.

 [10] J. Lin, H. Li, C. Nam, J.A. Szpunar, Analysis on volume fraction and crystal orientation relationship of monoclinic and tetragonal oxide grown on Zr–2.5Nb alloy, Journal of Nuclear Materials, 334 (2004) 200–206.

 [11] K.H. Ewald, U. Anselmi-Tamburini, Z.A. Munir, Combustion of zirconium powders in oxygen, Materials Science and Engineering A, 291 (2000) 118–130.

 [12] H. Frank, Transport properties of zirconium alloy oxide films, Journal of Nuclear Materials, 306 (2002) 85–98.

 

Keywords

Zirconium clad
Surface treatment
Corrosion resistance
 [1] T.R. Allen, R.J.M. Konings, A.T. Motta, Corrosion of Zirconium Alloys, Comprehensive Nuclear Materials, Oxford: Elsevier, (2012) 49-68.
 [2] ASM Handbook, Surface engineering, 5, Surface Cleaning, Finishing, and Coating (1996).
 [3] J.S. Forster, P.S. Philli, T.K. Di Alexander, R.L. Tapping, T. Laursen, J.R. Leslie, The effect of anodic oxidation on near-surface deuterium in Zr-2.5 wt.% Nb. Nuclear Instruments and ethods in Physics Research Section B: Beam Interactions with Materials and Atoms, 48(1-4) (1990) 4.
 [4] G.A. McRae, M.A. Maguire, C.A. Jeffrey, D.A. Guzonas, C.A. Brown, A comparison of fractal dimensions determined from atomic force microscopy and impedance spectroscopy of anodic oxides on Zr–2.5Nb, Applied Surface Science, 191(1-4) (2002) 10.
 [5] F. Rosalbino, D. Maccio, A. Saccone, E. Angelini, Effect of Nb alloying additions on the characteristics of anodic oxide films on zirconium and their stability in NaOH solution, Journal of Solid State Electrochemistry, 14(8) (2010) 5.
 [6] A. Nikulina, S. Shishov, B. Cox, F. Garzalli, P. Rudling, Manufacturing of Zr-Nb Alloys, ZIRAT-special topic report (2006). 
[7] International Atomic Energy Agency, Waterside corrosion of zirconium alloys in nuclear power plants, IAEA-TECDOC-996, Vienna January (1998).
 [8] J. Godlewski, J.P. Gross, M. Lambertin, M. Wadier, J.F. Weidinger, Proceedings of 9th International Symposium on Zirconium in the Nuclear Industry, ASTM-STP, 1132 (1991) 416.
 [9] D. Pecheur, J. Godlewski, J. Peybernes, L. Fayette, M. Noe, A. Frichet, O. Kerrec, Proceedings of 12th International Symposium on Zirconium in the Nuclear Industry, ASTM STP, 1354 (1998) 793.
 [10] J. Lin, H. Li, C. Nam, J.A. Szpunar, Analysis on volume fraction and crystal orientation relationship of monoclinic and tetragonal oxide grown on Zr–2.5Nb alloy, Journal of Nuclear Materials, 334 (2004) 200–206.
 [11] K.H. Ewald, U. Anselmi-Tamburini, Z.A. Munir, Combustion of zirconium powders in oxygen, Materials Science and Engineering A, 291 (2000) 118–130.
 [12] H. Frank, Transport properties of zirconium alloy oxide films, Journal of Nuclear Materials, 306 (2002) 85–98.

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