Korean Journal of Materials Research (한국재료학회지)

Materials Research Society of Korea (한국재료학회)
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Tensile Properties of Zr-0.4Sn-1.5Nb-0.2Fe

Zr-0.4Sn-1.5Nb-0.2Fe 합금의 인장특성

  • 이명호 (한국원자력연구소 지르코늄신합금핵연료피복관개발팀) ;
  • 김준환 (한국원자력연구소 지르코늄신합금핵연료피복관개발팀) ;
  • 최병권 (한국원자력연구소 지르코늄신합금핵연료피복관개발팀) ;
  • 정용환 (한국원자력연구소 지르코늄신합금핵연료피복관개발팀)
  • Published : 2004.10.01
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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.

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References

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