DOI QR코드

DOI QR Code

CORRELATION BETWEEN THE TENSILE STRENGTH AND CORROSION BEHAVIOR OF HEAT TREATED ZR-1.0NB ALLOY

  • Published : 2008.10.31

Abstract

The correlation between the tensile strength and corrosion behavior of Zr-1.0wt%Nb alloy heat treated at $480^{\circ}C$ for up to 32 hours was evaluated. The tensile strength at $400^{\circ}C$ was continuously reduced with an increasing heat treatment time, mainly due to a grain growth and a decreased area fraction of the precipitates. However, the corrosion resistance in an aqueous ammonia solution at $360^{\circ}C$ was enhanced, mainly due to the formation of $\beta$-Nb precipitates. It is thus concluded that a longer heat treatment time provides a better corrosion resistance while degrading the tensile strength.

Keywords

References

  1. T. K. Kim, C. T. Lee, and D. S. Sohn, 'Sintering Behavior of U-80 at.%Zr Powder Compacts in a Vacuum Environment', J. Nucl. Mater. 372, 394 (2008) https://doi.org/10.1016/j.jnucmat.2007.04.043
  2. B. H. Lee, J. S. Cheon, Y. H. Koo, J. Y. Oh, J. S. Yim, D. S. Sohn, M. Baryshnikov, and A. Gaiduchenko, 'Measurement of the Specific Heat of Zr-40 wt%U Metallic Fuel', J. Nucl. Mater. 360, 315 (2007) https://doi.org/10.1016/j.jnucmat.2006.10.023
  3. J. S. Kim, Y. S. Jeon, S. D. Park, B. C. Song, S. H. Han, and J. G. Kim, 'Dissolution and Burnup Determination of Irradiated U-Zr Alloy Nuclear Fuel by Chemical Methods', Nucl. Eng. Tech. 38, 301 (2006)
  4. G. L. Hofman, L. C. Walters, and T. H. Bauer, 'Metallic Fast Reactor Fuels', Prog. Nucl. Ener. 31, 83 (1997) https://doi.org/10.1016/0149-1970(96)00005-4
  5. C. T. Lee, J. H. Park, T. K. Kim, U. J. Lee, B. S. Lee, and D. S. Sohn, 'Thermal Stability of Co-Extruded U-Zr/Zr-Nb Alloys', J. Nucl. Mater. 373, 275 (2008) https://doi.org/10.1016/j.jnucmat.2007.06.006
  6. S. M. McDeavitt, and A. A. Solomon, 'Hot-isostatic Pressing of U-10Zr by a Coupled Grain Boundary Diffusion and Creep Cavitation Mechanism', J. Nucl. Mater. 228, 184 (1996) https://doi.org/10.1016/S0022-3115(95)00220-0
  7. K. Nakamura, T. Ogata, M. Kurata, A. Itoh, and M. Akabori, 'Reactions of U-Zr Alloy with Fe and Fe-Cr Alloy', J. Nucl. Mater. 275, 246 (1999) https://doi.org/10.1016/S0022-3115(99)00227-5
  8. H. G. Kim, S. Y. Park, M. H. Lee, Y. H. Jeong, and S. D. Kim, 'Corrosion and Microstructural Characteristics of Zr-Nb Alloys with different Nb Contents', J. Nucl. Mater. 373, 429 (2008) https://doi.org/10.1016/j.jnucmat.2007.05.035
  9. S.W. Ha, J.Y. Huh, J.Y. Park, and Y.H. Jeong, 'The Correlation of Annealing Parameter and Microstructures on Corrosion Characteristics and Mechanical Properties of Zr-1.0Nb Alloy', J. Kor. Inst. Met.& Mater. 39, 1092 (2001)
  10. Y. H. Kim, J. H. Baek, and Y. H. Jeong, 'Effects of Nb Contents and Final Annealing Temperatures on the Corrosion Characteristics of Nb-containing Zr Alloys', J. Kor. Inst. Met. & Mater. 40, 1173 (2002)
  11. H. G. Kim, Y. S. Lim, M. Y. Wey, and Y. H. Jeong, 'Effect of Niobium on the Microstructure and Corrosion Characteristics of Zr-xNb Binary Alloys', J. Kor. Inst. Met. & Mater. 37, 584 (1999)
  12. Y. H. Kim, M. Y. Wey, J. H. Baek, and Y. H. Jeong, 'Effects of Annealing Temperature and Sn Content on the Microstructure and Corrosion of Zr-1.5Nb-xSn Alloys', J. Kor. Inst. Met. & Mater. 42, 167 (2004)
  13. Y. H. Jeong, H. G. Kim, and T. H. Kim, 'Effect of $\beta$ Phase, Precipitate and Nb-concentration in Matrix on Corrosion and Oxide Characteristics of Zr-xNb Alloys', J. Nucl. Mater. 317, 1 (2003) https://doi.org/10.1016/S0022-3115(02)01676-8
  14. Y. H. Jeong, K. O. Lee, and H. G. Kim, 'Correlation between Microstructure and Corrosion Behavior of Zr-Nb Binary Alloy', J. Nucl. Mater. 302, 9 (2002) https://doi.org/10.1016/S0022-3115(02)00703-1
  15. Y. H. Jeong, H. G. Kim, D. J. Kim, B. K. Choi, and J. H. Kim, 'Influence of Nb Concentration in the $\alpha$-Matrix on the Corrosion Behavior of Zr-xNb Binary Alloys', J. Nucl. Mater. 323, 72 (2003)
  16. T. K. Kim, S. K. Yang, P. S. Choi, C. T. Lee, and D. S. Sohn, 'Effects of Heat Treatment on the Tensile Strength and Corrosion Resistance of Extruded Zr-Nb Alloy', J. Kor. Inst. Met. & Mater. 44, 823 (2006)
  17. M. Tupin, M. Pijolat, F. Valdivieso, M. Soustelle, A. Frichet, and P. Barberis, 'Differences in Reactivity of Oxide Growth during the Oxidation of Zircaloy-4 in Water Vapour before and after the Kinetic Transition', J. Nucl. Mater. 317, 140 (2003)