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Volume 36 Issue 1
Feb.  2025
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LI Quan, JIAO Yongjun, YU Junchong. Simulation of Subcooled Boiling and Critical Heat Flux in Uniformly Heated Tubes[J]. Nuclear Power Engineering, 2015, 36(1): 168-172. doi: 10.13832/j.jnpe.2015.01.0168
Citation: LI Quan, JIAO Yongjun, YU Junchong. Simulation of Subcooled Boiling and Critical Heat Flux in Uniformly Heated Tubes[J]. Nuclear Power Engineering, 2015, 36(1): 168-172. doi: 10.13832/j.jnpe.2015.01.0168

Simulation of Subcooled Boiling and Critical Heat Flux in Uniformly Heated Tubes

doi: 10.13832/j.jnpe.2015.01.0168
  • Received Date: 2014-11-27
  • Rev Recd Date: 2014-12-15
  • Available Online: 2025-02-15
  • Based on Eulerian two-fluid framework and non-equilibrium subcooled boiling model, the numerical model is established to simulate the subcooled boiling. This model is used to simulate the subcooled flow and CHF of DNB type in uniformly heated tubes. The numerical model is proved correct by comparing to the subcooled flow experiment of Bartolomei. The boiling curves is calculated, and it is suggested to treat the first point in the critical area of boiling curves as the criterion of DNB. 12 CHF points drawn from the latest 2006 CHF look-up table are simulated. These 12 points are chosen with different mass flux, pressure or local equilibrium quality, but all are under high pressures and high mass flux. The CHF predicted confirm well to the experiment and the location that CHF occur is also well captured.

     

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