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http://dx.doi.org/10.3740/MRSK.2004.14.10.713

Tensile Properties of Zr-0.4Sn-1.5Nb-0.2Fe  

Lee M. H. (Advanced Zr Alloy Development, KAERI)
Kim J. H. (Advanced Zr Alloy Development, KAERI)
Choi B. K. (Advanced Zr Alloy Development, KAERI)
Jeong Y. H. (Advanced Zr Alloy Development, KAERI)
Publication Information
Korean Journal of Materials Research / v.14, no.10, 2004 , pp. 713-718 More about this Journal
Abstract
To study the dynamic strain aging behavior of Zr-0.4Sn-1.5Nb-0.2Fe sample tube for nuclear fuel cladding in the range of pressurized water reactor (PWR) operation temperature, the tensile tests of the tube specimens, which had been finally heat-treated at $470^{\circ}C\;and\;510^{\circ}C$, had been carried out with the strain rate $1.67{\times}10^{-2}/s\;and\;8.33{\times}10^{-5}/s$ at the various temperatures from room temperature to $500^{\circ}C$. It was observed that the elongation of the specimens got shortened as the temperature increased from $200^{\circ}C\;to\;340^{\circ}C$. The specimens that were finally heat-treated at $470^{\circ}C$ showed a plateau more remarkably on the plot of yield strength-temperature than those heat-treated at $510^{\circ}C$. In the range of $310\sim400^{\circ}C$, the strain rate sensitivity of the specimens finally heat-treated at $510^{\circ}C$ was $30.4\%\sim33.7\%$ lower but the work hardening exponent index of the specimens was a little higher than that without dynamic strain aging effect.
Keywords
cladding tube; Zr-based alloy; dynamic strain aging;
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
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