Neutronic and Thermal-Hydraulic Performance Analysis of Helical Cruciform Fuel Rods

Zhang Tao; Han Wenbin; Shen Pengfei; Huang Shanfang; Wang Kan

doi:10.13832/j.jnpe.2023.S1.0069

Volume 44 Issue S1

Jun. 2023

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Zhang Tao, Han Wenbin, Shen Pengfei, Huang Shanfang, Wang Kan. Neutronic and Thermal-Hydraulic Performance Analysis of Helical Cruciform Fuel Rods[J]. Nuclear Power Engineering, 2023, 44(S1): 69-74. doi: 10.13832/j.jnpe.2023.S1.0069

Citation:

Zhang Tao, Han Wenbin, Shen Pengfei, Huang Shanfang, Wang Kan. Neutronic and Thermal-Hydraulic Performance Analysis of Helical Cruciform Fuel Rods[J]. Nuclear Power Engineering, 2023, 44(S1): 69-74. doi: 10.13832/j.jnpe.2023.S1.0069

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Neutronic and Thermal-Hydraulic Performance Analysis of Helical Cruciform Fuel Rods

doi: 10.13832/j.jnpe.2023.S1.0069

1.
Department of Engineering Physics, Tsinghua University, Beijing, 100084, China
2.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2023-02-21
Rev Recd Date: 2023-05-24
Publish Date: 2023-06-15

Abstract

Abstract

To analyze the neutronic and thermal-hydraulic performance of helical cruciform fuel (HCF) rods, numerical simulations using the CAD (computer-aided design)-based Reactor Monte Carlo code RMC and the commercial computational fluid dynamics (CFD) software Fluent were conducted, and the results were compared with those of traditional cylindrical and untwisted cruciform fuel rods. The results show that the helical cruciform structure slightly reduces the reactivity and increases the radial power peaking factor. Compared with cylindrical fuel rods, the HCF rods can enhance coolant mixing and heat transfer due to their transverse flow characteristics. In the 7-rods assembly calculation, the mean and peak temperatures of HCF rods are reduced by about 4 K.
- Helical cruciform fuel rods,
- Monte Carlo method,
- Computational Fluid Dynamics (CFD),
- Flow and heat transfer characteristics

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References(18)

References

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