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Volume 44 Issue 4
Aug.  2023
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Xing Shuo, Pu Zengping, Zhang Kun, Jiao Yongjun, Dai Xun, He Liang. Study on Evaluation Method for Creep Performance of New Zirconium Alloy Cladding[J]. Nuclear Power Engineering, 2023, 44(4): 234-239. doi: 10.13832/j.jnpe.2023.04.0234
Citation: Xing Shuo, Pu Zengping, Zhang Kun, Jiao Yongjun, Dai Xun, He Liang. Study on Evaluation Method for Creep Performance of New Zirconium Alloy Cladding[J]. Nuclear Power Engineering, 2023, 44(4): 234-239. doi: 10.13832/j.jnpe.2023.04.0234

Study on Evaluation Method for Creep Performance of New Zirconium Alloy Cladding

doi: 10.13832/j.jnpe.2023.04.0234
  • Received Date: 2023-04-12
  • Rev Recd Date: 2023-05-29
  • Publish Date: 2023-08-15
  • In order to establish a creep model for new zirconium alloy, based on the data from creep test, the creep behavior of the new zirconium alloy cladding tubes at the temperature of 593-673K and the stress of 60-160 MPa was investigated. The classical zirconium alloy creep model was used to predict the creep behavior of the new zirconium alloy clad tube. Based on the constitutive equation of creep behavior, a preliminary evaluation method of creep of new zirconium alloy cladding tube was studied and established, and the preliminary verification was carried out. The verification results show that the predicted values are in good agreement with the measured values, and the maximum relative deviation is whithin 25%. The model is in agreement with the change of creep behavior of zirconium alloy in reactor. In this study, a new zirconium alloy cladding creep model is established, and the model is in agreement with the change of the in-core creep behavior of the zirconium alloy, which provides support for the prediction of the new zirconium alloy's in-reactor behavior.

     

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