Korean Journal of Metals and Materials (대한금속재료학회지)

The Korean Institute of Metals and Materials (대한금속재료학회)
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Evaluation of Hydride Effect on Fuel Cladding Degradation

피복관 열화거동에 미치는 수소화물 영향 평가

  • Kim, Hyun-Gil (Nuclear Convergence Technology Division, Korea Atomic Energy Research Institute) ;
  • Kim, Il-Hyun (Nuclear Convergence Technology Division, Korea Atomic Energy Research Institute) ;
  • Park, Sang-Yoon (Nuclear Convergence Technology Division, Korea Atomic Energy Research Institute) ;
  • Park, Jeong-Yong (Nuclear Convergence Technology Division, Korea Atomic Energy Research Institute) ;
  • Jeong, Yong-Hwan (Nuclear Convergence Technology Division, Korea Atomic Energy Research Institute)
  • 김현길 (한국원자력연구원 원자력융합기술개발부) ;
  • 김일현 (한국원자력연구원 원자력융합기술개발부) ;
  • 박상윤 (한국원자력연구원 원자력융합기술개발부) ;
  • 박정용 (한국원자력연구원 원자력융합기술개발부) ;
  • 정용환 (한국원자력연구원 원자력융합기술개발부)
  • Received : 2010.03.16
  • Published : 2010.08.22
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Abstract

The degradation behavior of fuel cladding is a very import concern in nuclear power generation, because the operation of nuclear plants can be limited by fuel cladding degradation. In order to evaluate the hydride effect on failure of zirconium fuel claddings, a ring tensile test for the circumferential direction was carried out at room temperature for claddings having different hydride characteristics such as density and orientation; microstructural evaluation was also performed for those claddings. The circumferential failure of the claddings was promoted by increasing the hydride concentration in the matrix; however, the failure of the claddings was affected by the hydride orientation rather than by the hydride concentration in the matrix. From fracture surface observation, the cladding failure during the ring tensile test was matched with the hydride orientation.

Keywords

Acknowledgement

Supported by : 교육과학기술부

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