Abstract
Zr–0.85Sn–0.16Nb–0.37Fe–0.18Cr alloy samples prepared by low-temperature process (LTP) and high-temperature process (HTP) show different corrosion behaviors in 500 °C steam. The former exhibits uniform corrosion, while the latter exhibits nodular corrosion casually. The occurrence of nodular corrosion on HTP samples is attributed to the formation of local alloying elements depletion region in the Zr matrix. During hot rolling at 800 °C, transformation of zirconium from α-phase to β-phase happens locally. Alloying elements migrate to β-phase from its neighboring α-phase. The local β-phase dissolves in the subsequent cold rolling and final annealing, leaving the microstructure with agglomeration of precipitate particles and neighboring alloying elements depletion regions in Zr matrix. And the undesirable microstructure becomes the causation of nodular corrosion.
Graphic Abstract
Similar content being viewed by others
References
B. Cox, Journal of Nuclear Materials 336, 2005 (331–368).
D. G. Franklin, in Zirconium in the Nuclear Industry: Sixteenth International Symposium, eds. M. Limback and P. Barberis (ASTM International, West Conshohocken, 2011), pp. 17–36.
N. Ramasubramanian, Journal of Nuclear Materials 119, 1983 (208–218).
A. W. Urquhart and D. A. Verilyea, Journal of Nuclear Materials 62, 1976 (111–114).
P. Rudling and G. Wikmark, Journal of Nuclear Materials 265, 1999 (44–59).
L. Lunde and K. Videm, in Zirconium in the Nuclear Industry: Fourth International Symposium, eds. T. H. Schemel and T. P. Papazoglon (ASTM International, West Conshohocken, 1979), pp. 40–49.
R. M. Kruger, R. B. Adamson and S. S. Brenner, Journal of Nuclear Materials 189, 1992 (193–200).
G. Maussner, E. Steinberg and E. Tenckhoff, in Zirconium in the Nuclear Industry: Seventh International Symposium, eds. R. B. Adamson and L. F. P. Van Swan (ASTM International, West Conshohocken, 1987), pp. 307–320.
D. Charquet, Journal of Nuclear Materials 288, 2001 (237–240).
B. Cheng and R. B. Adamson, in Zirconium in the Nuclear Industry: Seventh International Symposium, eds. R. B. Adamson and L. F. P. Van Swan (ASTM International, West Conshohocken, 1987), pp. 387–416.
K. Ogata, in Zirconium in the Nuclear Industry: Eighth International Symposium, eds. L. F. R. Van Swan and C. M. Eucken (ASTM International, West Conshohocken, 1987), pp. 346–359.
D. Charquet, B. Tricot and J.-F. Wadier, in Zirconium in the Nuclear Industry: Eighth International Symposium, eds. L. F. R. Van Swan and C. M. Eucken (ASTM International, West Conshohocken, 1989), pp. 374–391.
S. J. Xie, B. X. Zhou, X. Liang, W. Q. Liu, H. Li, Q. Li, M. Y. Yao and J. L. Zhang, Corrosion Science 126, 2017 (44–54).
B. X. Zhou, M. Y. Yao, Q. Li, S. Xia, W. Q. Liu and Y. L. Chu, Rare Metal Materials and Engineering 36, 2007 (1317–1321).
Y. H. Jeong, H. G. Kim, D. J. Kim, B. K. Choi and J. H. Kim, Journal of Nuclear Materials 323, 2003 (72–80).
S. J. Kim, H. S. Hong and Y. M. Oh, Journal of Nuclear Materials 306, 2002 (194–201).
C. Toffolon-Masclet, T. Guilbert and J. G. Brachet, Journal of Nuclear Materials 372, 2008 (367–378).
T. G. Wei, C. S. Long and H. S. Chen, The Journal of Alloys and Compounds 731, 2018 (126–134).
J. Wang, H. Y. Fan, J. Xiong, H. Liu, Z. Miao, S. H. Ying and G. Yang, Nuclear Engineering and Design 241, 2011 (471–475).
D. F. Taylor, Journal of Nuclear Materials 277, 2000 (295–314).
Y. Etoh, Journal of Nuclear Science and Technology 26, 1989 (752–759).
A. T. Motta, A. Yilmazbayhan, M. J. Gomes da Silva, R. J. Comstock, G. S. Was, J. T. Busby, E. Gartner, Q. Peng, Y. H. Jeong and J. Y. Park, Journal of Nuclear Materials 371, 2007 (61–75).
B. X. Zhou, in Zirconium in the Nuclear Industry: Eighth International Symposium, eds. L. F. R. Van Swan and C. M. Eucken (ASTM International, West Conshohocken, 1989), pp. 360–373.
D. J. Park and J. Y. Park, Corrosion Science 69, 2013 (61–66).
D. J. Park, J. Y. Park and Y. H. Jeong, Journal of Nuclear Materials 412, 2011 (233–238).
A. T. Motta, M. J. Gomes da Silva, A. Yilmazbayhan, R. J. Comstock, Z. Cai and B. Lai, in Zirconium in the Nuclear Industry: Fifth International Symposium, eds. B. Kammenzind and M. Limback (ASTM International, West Conshohocken, 2008), pp. 486–505.
Y. Dali, M. Tupin, P. Bossis, M. Pijolat, Y. Wouters and F. Jomard, Journal of Nuclear Materials 426, 2012 (148–159).
P. Hurst and C. Tyzack, Effect of Enviroment on Material Properties in Nuclear Systems, (Institution of Civil Engineers, London, 1971), pp. 37–49.
B. Cheng, H. A. Levin, R. B. Adamson, M. O. Marlowe and V. L. Monroe, in Zirconium in the Nuclear Industry: Seventh International Symposium, eds. R. B. Adamson and L. F. P. Van Swan (ASTM International, West Conshohocken, 1987), pp. 257–283.
D. M. Rishel, K. L. Eklund and B. F. Kammenzind, in Zirconium in the Nuclear Industry: Eighth International Symposium, eds. B. Kammenzind and M. Limback (ASTM International, West Conshohocken, PA, 1987), pp. 326–359.
Acknowledgements
This research is funded by the National Natural Science Foundation of China (No. 51801195). The authors want to acknowledge their collaborators from Northwestern Institute for Non Ferrous Metals (Xi’ an, China) for the preparation of materials.
Author information
Authors and Affiliations
Corresponding author
Additional information
Publisher's Note
Springer Nature remains neutral with regard to jurisdictional claims in published maps and institutional affiliations.
Rights and permissions
About this article
Cite this article
Wei, T., Dai, X., Chen, B. et al. Nodular Corrosion of Zr–0.85Sn–0.16Nb–0.37Fe–0.18Cr Alloy in 500 °C Steam Caused by High-temperature Processing. Oxid Met 92, 493–504 (2019). https://doi.org/10.1007/s11085-019-09936-8
Received:
Revised:
Published:
Issue Date:
DOI: https://doi.org/10.1007/s11085-019-09936-8