DOI QR코드

DOI QR Code

Corrosion Behavior of Zirconium Alloys with Nb and Cr Addition

Nb 및 Cr 첨가에 따른 지르코늄 합금의 부식거동

  • Received : 2015.06.29
  • Accepted : 2015.07.16
  • Published : 2015.08.27

Abstract

The effects of Nb and Cr addition on the microstructure, corrosion and oxide characteristics of Zr based alloys were investigated. The corrosion tests were performed in a pressurized water reactor simulated-loop system at $360^{\circ}C$. The microstructures were examined using OM and TEM, and the oxide properties were characterized by low-angle X-ray diffraction and TEM. The corrosion test results up to 360 days revealed that the corrosion rates were considerably affected by Cr content but not Nb content. The corrosion resistance of the Zr-xNb-0.1Sn-yCr quaternary alloys was improved by an increasing Nb/Cr ratio. The crystal structure of the precipitates was affected by a variation of the Nb/Cr ratio. The Zr-Nb beta-enriched precipitates were mainly formed in the high Nb/Cr ratio alloy while $Zr(NbCr)_2$ precipitates were frequently observed in the low Nb/Cr ratio alloy. The studies of oxide characteristics revealed that the corrosion resistance was related to the crystal structure of the precipitate.

Keywords

References

  1. R. J. Comstock, G. Schoenberger and G. P. Sabol, Zirconium in the Nuclear Industry, ASTM STP 1295, 710 (1996).
  2. J. P. Mardon, D. Charquet and J. Senevat, Zirconium in the Nuclear Industry, ASTM STP 1354, 505 (2000).
  3. E. R. Bradley and G. P. Sabol, Zirconium in the Nuclear Industry, ASTM STP 1295, 603 (1996).
  4. H. G. Kim, J. Y. Park, Y. H. Jeong, Y. H. Koo, J. S. Yoo, Y. K. Mok, Y. H. Kim and J. M. Suh, Nucl. Eng. Technol., 46(3), 423 (2013). https://doi.org/10.5516/NET.07.2013.093
  5. H. G. Kim, S. Y. Park, M. H. Lee, Y. H. Jeong and S. D. Kim, J. Nucl. Mater., 373, 429 (2008). https://doi.org/10.1016/j.jnucmat.2007.05.035
  6. F. Garzarolli, H. Stehle, and E. Steinberg, Zirconium in the Nuclear Industry, ASTM STP 1295, 12 (1996).
  7. H. G. Kim, J. Y. Park and Y. H. Jeong, J. Nucl. Mater., 345, 1 (2005). https://doi.org/10.1016/j.jnucmat.2005.04.061
  8. ASTM G2-81 Vol. 12.2 (1987).
  9. C. E. Lundin and R. H. Cox, USAEC Report, GEAP-4089 1, 9 (1962).
  10. H. G. Kim, Y. H. Jeong and T. H. Kim, J. Nucl. Mater., 326, 125 (2004). https://doi.org/10.1016/j.jnucmat.2004.01.015
  11. J. B. Vander Sander and A. L. Bement, J. Nucl. Mater., 52, 115 (1974). https://doi.org/10.1016/0022-3115(74)90032-4
  12. J. Godlewski, Zirconium in the Nuclear Industry, ASTM STP 1245, 663 (1994).