Korean Journal of Materials Research (한국재료학회지)

Materials Research Society of Korea (한국재료학회)
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Effects of Oxide Growth on Mechanical Properties Degradation of Zirconium Alloys

산화막 성장이 지르코늄 합금의 기계적 물성 열화에 미치는 영향

  • Jeon Sang-hwan (Department of Nuclear Engineering, Hanyang University) ;
  • Kim Yong-soo (Department of Nuclear Engineering, Hanyang University)
  • 전상환 (한양대학교 원자력공학과) ;
  • 김용수 (한양대학교 원자력공학과)
  • Published : 2004.08.01
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Abstract

A study on the effects of oxide growth on the mechanical properties degradation of pure zirconium and Zircaloy-4 is carried out with high temperature tensile tests. It is found that the mechanical properties can deteriorate with the oxide growth less than $1\%$ of total specimen cross section, especially at $300\~400^{\circ}C$ that is zirconium alloy cladding temperature during the nuclear reactor operation. It is also revealed that Young's modulus changes little but yield strength and tensile strength drop down to $20\% and 40\%$ of the room temperature strength, respectively, in the temperature range. Fractographic analysis shows that the number of dimples decreases and fractured surface becomes smooth with increasing oxide thickness.

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References

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