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Volume 27 Issue 5
Oct.  2006
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FAN Pu, QIU Sui-zheng, JIA Dou-nan. Investigation of Critical Heat Flux of Annular Flow in Vertical Upward Round Tube[J]. Nuclear Power Engineering, 2006, 27(5): 42-47.
Citation: FAN Pu, QIU Sui-zheng, JIA Dou-nan. Investigation of Critical Heat Flux of Annular Flow in Vertical Upward Round Tube[J]. Nuclear Power Engineering, 2006, 27(5): 42-47.

Investigation of Critical Heat Flux of Annular Flow in Vertical Upward Round Tube

  • Received Date: 2005-07-18
  • Rev Recd Date: 2005-10-24
  • Available Online: 2025-07-29
  • Prediction of Critical Heat Flux at high mass quality is important for the safety of once-through steam generator and the reactor core under accidental conditions.Based on the theory for droplet entrainment,droplet deposition and liquid film evaporation,the film thickness and film mass flow rate dis-tribution along axis are calculated at vertical upward round tube.The dryout emerges at the point where the film is depleted due to the balance of entrainment,deposition and evaporation.The theoretical CHF values are higher than that of experimental data,with error within 30%.

     

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