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Volume 42 Issue S2
Dec.  2021
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Liu Wei, Peng Shinian, Jiang Guangming, Liu Yu. Development and Verification of a Comprehensive Rod Bundle CHF Mechanism Model[J]. Nuclear Power Engineering, 2021, 42(S2): 77-81. doi: 10.13832/j.jnpe.2021.S2.0077
Citation: Liu Wei, Peng Shinian, Jiang Guangming, Liu Yu. Development and Verification of a Comprehensive Rod Bundle CHF Mechanism Model[J]. Nuclear Power Engineering, 2021, 42(S2): 77-81. doi: 10.13832/j.jnpe.2021.S2.0077

Development and Verification of a Comprehensive Rod Bundle CHF Mechanism Model

doi: 10.13832/j.jnpe.2021.S2.0077
  • Received Date: 2021-07-19
  • Accepted Date: 2021-12-06
  • Rev Recd Date: 2021-10-26
  • Publish Date: 2021-12-29
  • In order to continuously and accurately predict departure from nucleate boiling (DNB) and dry-out (DO) type critical heat flux (CHF) under wide parameter range for rod bundle channel, a comprehensive rod bundle CHF mechanism model covering different types of CHF based on the CHF classification criterion in the bundle channel and the mechanism model of DNB type CHF for evaporation of superheated liquid layer and combined with the mature DO type CHF mechanism model that has been studied. The 5 × 5 full-length rod bundle CHF experimental data of Nuclear Power Institute of China (NPIC) is used to verify the CHF mechanism model of the comprehensive rod bundle. The results show that all predicted value/measured value (P/ M ) data of the comprehensive rod bundle CHF mechanism model are evenly distributed around 1, and the maximum relative deviation is within ± 22%, indicating that the developed comprehensive rod bundle CHF mechanism model can continuously and accurately predict the DNB and DO type CHF in rod bundle channel.

     

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