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Volume 46 Issue 4
Aug.  2025
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Zhang Qi, Liu Zhenhai, Li Chenxi, Wang Haoyu, Fu Junsen, Li Junlong, Huang Yongzhong, Xiao Yao, Gu Hanyang. Development and Validation of the Sub-channel Code for Helical Cruciform Fuel Assembly of PWR[J]. Nuclear Power Engineering, 2025, 46(4): 94-101. doi: 10.13832/j.jnpe.2024.080009
Citation: Zhang Qi, Liu Zhenhai, Li Chenxi, Wang Haoyu, Fu Junsen, Li Junlong, Huang Yongzhong, Xiao Yao, Gu Hanyang. Development and Validation of the Sub-channel Code for Helical Cruciform Fuel Assembly of PWR[J]. Nuclear Power Engineering, 2025, 46(4): 94-101. doi: 10.13832/j.jnpe.2024.080009

Development and Validation of the Sub-channel Code for Helical Cruciform Fuel Assembly of PWR

doi: 10.13832/j.jnpe.2024.080009
  • Received Date: 2024-08-12
  • Rev Recd Date: 2024-10-14
  • Publish Date: 2025-08-15
  • In order to develop the sub-channel code for the helical cruciform fuel (HCF) assembly of PWR, the frictional model and heat transfer model of the HCF assembly is introduced into the COBRA-TF code, the two-way mixing of the first type of rod gap and the one-way mixing of the second type of rod gap is predicted by two groups of momentum equations, the accuracy of new code is validated with the experimental data and numerical simulation results, and the axial distribution of the wall temperature, the mass flux distribution et al. of the HCF assembly are analyzed. According to the study results, the distribution of the thermal-hydraulic parameters of the HCF assembly can be accurately predicted by the new code, and the new code can be used for the calculation and analysis of the large-scale fuel assembly. This study provides a reliable analysis tool for the development and application of the HCF assembly.

     

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