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Volume 31 Issue 3
Jun.  2010
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ZHAO Da-wei, SU Guang-hui, QIU Sui-zheng. Prediction of Critical Heat Flux in Vertical Tube under Flow Oscillation Condition[J]. Nuclear Power Engineering, 2010, 31(3): 36-39.
Citation: ZHAO Da-wei, SU Guang-hui, QIU Sui-zheng. Prediction of Critical Heat Flux in Vertical Tube under Flow Oscillation Condition[J]. Nuclear Power Engineering, 2010, 31(3): 36-39.

Prediction of Critical Heat Flux in Vertical Tube under Flow Oscillation Condition

  • Received Date: 2009-03-10
  • Rev Recd Date: 2010-01-15
  • Available Online: 2025-07-29
  • Publish Date: 2010-06-01
  • The reduction limit of critical heat flux(CHF) in vertical tube under flow oscillation condition,obtained by a temperature response model,was modified using the CHF experimental data of Umekawa and Ozawa et al..Based on the modified reduction limit of CHF,a new correlation was proposed to predict the CHF under flow oscillation condition in vertical tubes at low velocity and pressure conditions.The comparisons between the prediction of the new correlation and experimental data show a reasonable agreement with a mean error of 11.5%,which is smaller than the error of prediction using Kim correlation,21.04%.

     

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