Investigation on the Flow and Heat Transfer Characteristics of Liquid Lead Cross-flow Tube Bundle under Cooling Conditions

Li Liangxing; Xu Xiangyang; Xiang Zutao; Shi Shang; Lei Zhenxin

doi:10.13832/j.jnpe.2025.01.0116

Volume 46 Issue 1

Feb. 2025

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Article Navigation > Nuclear Power Engineering > 2025 > 46(1): 116-127

Li Liangxing, Xu Xiangyang, Xiang Zutao, Shi Shang, Lei Zhenxin. Investigation on the Flow and Heat Transfer Characteristics of Liquid Lead Cross-flow Tube Bundle under Cooling Conditions[J]. Nuclear Power Engineering, 2025, 46(1): 116-127. doi: 10.13832/j.jnpe.2025.01.0116

Citation:

Li Liangxing, Xu Xiangyang, Xiang Zutao, Shi Shang, Lei Zhenxin. Investigation on the Flow and Heat Transfer Characteristics of Liquid Lead Cross-flow Tube Bundle under Cooling Conditions[J]. Nuclear Power Engineering, 2025, 46(1): 116-127. doi: 10.13832/j.jnpe.2025.01.0116

Citation:

Li Liangxing, Xu Xiangyang, Xiang Zutao, Shi Shang, Lei Zhenxin. Investigation on the Flow and Heat Transfer Characteristics of Liquid Lead Cross-flow Tube Bundle under Cooling Conditions[J]. Nuclear Power Engineering, 2025, 46(1): 116-127. doi: 10.13832/j.jnpe.2025.01.0116

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Investigation on the Flow and Heat Transfer Characteristics of Liquid Lead Cross-flow Tube Bundle under Cooling Conditions

doi: 10.13832/j.jnpe.2025.01.0116

State Key Laboratory of Multiphase Flow in Power Engineering, Xi’an Jiaotong University, Xi’an, 710049, China

Received Date: 2024-03-17
Rev Recd Date: 2024-05-12
Publish Date: 2025-02-15

Abstract

Abstract

The flow and heat transfer characteristics of liquid metal coolant in the primary heat exchanger are of great importance to the economic and safe operation of lead-cooled fast reactor. According to the arrangement characteristics of tube bundle in a spiral coil heat exchanger, the present study established a two-dimensional analysis model for liquid lead cross-flow tube bundle. The turbulent Prandtl number model suitable for the flow of liquid lead cross-flow tube bundle is compared and analyzed, and the flow and heat transfer characteristics of liquid lead cross-flow scouring heat exchanger tube bundle are studied by numerical simulation. The results show that with the increase of inlet Reynolds number, the concave degree of the time-average velocity distribution curve of liquid lead among tubes increases, and the difference of dimensionless wall temperature enlarges in the return area, while the vortex disturbance is enhanced to the area around 180° of the tube walls. The comprehensive flow and heat transfer performance of liquid lead transversally scouring tube bundles has a positive correlation with the transverse pitch diameter ratio of the spiral coil and a negative correlation with the inlet Reynolds number. Based on the numerical simulation, the heat transfer correlation of liquid lead transversally scouring tube bundles is proposed, and its prediction error is less than 10%.
- Lead-cooled fast reactor,
- Liquid lead,
- Transversally scouring tube bundle,
- Flow and heat transfer characteristics,
- Primary heat exchanger

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References(25)

References

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