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Volume 45 Issue S2
Jan.  2025
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Liu Zhenhai, Zhou Yi, Qi Feipeng, Xin Yong, Li Wenjie, Gong Zhaohu, Zeng Wei, Zhang Tao. Study on Non-classical PCMI Behavior Based on FUPAC3D[J]. Nuclear Power Engineering, 2024, 45(S2): 77-83. doi: 10.13832/j.jnpe.2024.S2.0077
Citation: Liu Zhenhai, Zhou Yi, Qi Feipeng, Xin Yong, Li Wenjie, Gong Zhaohu, Zeng Wei, Zhang Tao. Study on Non-classical PCMI Behavior Based on FUPAC3D[J]. Nuclear Power Engineering, 2024, 45(S2): 77-83. doi: 10.13832/j.jnpe.2024.S2.0077

Study on Non-classical PCMI Behavior Based on FUPAC3D

doi: 10.13832/j.jnpe.2024.S2.0077
  • Received Date: 2024-08-13
  • Rev Recd Date: 2024-10-11
  • Publish Date: 2025-01-06
  • For the fuel rods of pressurized water reactor, strong mechanical interaction between the fuel pellet and cladding (PCMI) occurs under Class Ⅱ transient. When the pellet exhibits missing surface defects, the interaction are further intensified. Traditional 1.5D fuel performance analysis codes cannot analyze this non-classical PCMI phenomenon. In this paper, the developed 3D fuel performance analysis code FUPAC3D is used for simulation. Taking the common pellet end missing surface defect in manufacturing as an example, the impact of defect on the heat transfer and mechanical behavior of the fuel rod during transient is analyzed. The results show that the temperature distribution around the cladding near the pellet defect is uneven, with increased temperature at the edge of the defect and decreased temperature in the center. The cladding near the defect is indented inwards, causing an increase in the hoop stress of the cladding near the center of the defect. Compared to the corresponding "bamboo joint" part (the pellet end) of a complete pellet, it increases by about 14.3%, and compared to the middle plane of the pellet, it increases by about 62.9%.

     

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