Nuclear Engineering and Technology

  • 제52권12호
  • /
  • Pages.2901-2909
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  • 2020
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  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Thermal creep behavior of CZ cladding under biaxial stress state

  • Jin, Xin (China Nuclear Power Technology Research Institute Co.,Ltd) ;
  • Lin, Yuyu (China Nuclear Power Technology Research Institute Co.,Ltd) ;
  • Zhang, Libin (China Nuclear Power Technology Research Institute Co.,Ltd)
  • 투고 : 2020.03.12
  • 심사 : 2020.05.26
  • 발행 : 2020.12.25
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초록

Thermal creep is a key property of zircaloy cladding. CZ developed by CGN is a new zircaloy used as PWR fuel cladding. This research is devoted to investigating the thermal creep behavior of CZ and build the thermal creep model of CZ. Twenty internal pressure creep tests were conducted, and the ranges of temperature and Tresca stress were 320-430 ℃ and 70-300 MPa, respectively. Real-time creep data were analyzed by separating primary creep and steady-state creep. Based on Soderberg model and creep test data, CZ thermal creep model is derived. As a whole, the mean value and the standard deviation of P/M of CZ saturated primary creep strain are very close to these from steady-state creep rate, however, the predictive effect of primary creep is less satisfactory. Four conditions, where there exists large deviation between predicted values and test data, are 320 ℃ and 300 MPa, 350 ℃ and 190 MPa, 380 ℃ and 160 MPa, 380 ℃ and 190 MPa, respectively. As primary creep was much smaller than steady-state creep in long-time operation, the thermal creep model built can be applied to predict the thermal creep behavior of CZ cladding.

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참고문헌

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