Embrittlement Behavior of Zirconium Alloy in Quenching Heat Treatment

급랭 열처리시 지르코늄 합금의 취성 거동

  • Kim, Jun Hwan (Zirconium Fuel Cladding Development Team, Korea Atomic Energy Research Institute) ;
  • Lee, Jong Hyuk (Zirconium Fuel Cladding Development Team, Korea Atomic Energy Research Institute) ;
  • Choi, Byoung Kwon (Zirconium Fuel Cladding Development Team, Korea Atomic Energy Research Institute) ;
  • Jeong, Yong Hwan (Zirconium Fuel Cladding Development Team, Korea Atomic Energy Research Institute)
  • 김준환 (한국원자력연구소 경수로연료개발부 지르코늄신합금 개발팀) ;
  • 이종혁 (한국원자력연구소 경수로연료개발부 지르코늄신합금 개발팀) ;
  • 최병권 (한국원자력연구소 경수로연료개발부 지르코늄신합금 개발팀) ;
  • 정용환 (한국원자력연구소 경수로연료개발부 지르코늄신합금 개발팀)
  • Received : 2004.03.10
  • Accepted : 2004.04.28
  • Published : 2004.07.30

Abstract

Study was focused on the quenching embrittlement property of Zircaloy-4 cladding simulated Loss Of Coolant Accident (LOCA) environment in terms of high temperature oxidation and phase transformation. Property in LOCA condition of advanced cladding that contained Nb element was also investigated. Claddings were oxidized at given temperature and given time followed by water quenching. The results showed that ${\beta}$ phase which formed at quenching stage has an influence on cladding property. In case of advanced cladding, Nb retards cladding oxidation, thus enhances quenching resistance.

Keywords

Acknowledgement

Supported by : 과학기술부

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