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http://dx.doi.org/10.5516/NET.2008.40.6.505

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

Kim, Tae-Kyu (Korea Atomic Energy Research Institute)
Choi, Pyung-Sik (Korea Atomic Energy Research Institute)
Yang, Sung-Ki (Korea Atomic Energy Research Institute)
Lee, Chong-Tak (Korea Atomic Energy Research Institute)
Sohn, Dong-Seong (Korea Atomic Energy Research Institute)
Publication Information
Nuclear Engineering and Technology / v.40, no.6, 2008 , pp. 505-510 More about this Journal
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
Zr-1.0wt%Nb Alloy; Tensile Strength; Corrosion Behavior;
Citations & Related Records
Times Cited By KSCI : 2  (Citation Analysis)
Times Cited By Web Of Science : 0  (Related Records In Web of Science)
Times Cited By SCOPUS : 0
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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)   DOI   ScienceOn
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)   DOI   ScienceOn
3 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)
4 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)   DOI   ScienceOn
5 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)   과학기술학회마을
6 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)   DOI   ScienceOn
7 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)
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)   DOI   ScienceOn
9 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)   DOI   ScienceOn
10 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)
11 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)
12 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)
13 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)   DOI   ScienceOn
14 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)
15 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)   DOI   ScienceOn
16 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)
17 G. L. Hofman, L. C. Walters, and T. H. Bauer, 'Metallic Fast Reactor Fuels', Prog. Nucl. Ener. 31, 83 (1997)   DOI   ScienceOn