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논문 기본 정보

자료유형
학술저널
저자정보
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)
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제52권 제12호
발행연도
2020.12
수록면
2,901 - 2,909 (9page)
DOI
https://doi.org/10.1016/j.net.2020.05.026

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초록· 키워드

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Thermal creep is a key property of zircaloy cladding. CZ developed by CGN is a new zircaloy used as PWRfuel cladding. This research is devoted to investigating the thermal creep behavior of CZ and build thethermal creep model of CZ. Twenty internal pressure creep tests were conducted, and the ranges oftemperature and Tresca stress were 320e430 C and 70e300 MPa, respectively. Real-time creep datawere analyzed by separating primary creep and steady-state creep. Based on Soderberg model and creeptest 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, thepredictive effect of primary creep is less satisfactory. Four conditions, where there exists large deviationbetween predicted values and test data, are 320 C and 300 MPa, 350 C and 190 MPa, 380 C and160 MPa, 380 C and 190 MPa, respectively. As primary creep was much smaller than steady-state creepin long-time operation, the thermal creep model built can be applied to predict the thermal creepbehavior of CZ cladding

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