Research on Hydraulic Performance of LFR Axial-flow Reacter Coolant Pump

Lyu Tianzhi; Yang Congxin; Guo Yanlei

doi:10.13832/j.jnpe.2023.S2.0126

Volume 44 Issue S2

Dec. 2023

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Lyu Tianzhi, Yang Congxin, Guo Yanlei. Research on Hydraulic Performance of LFR Axial-flow Reacter Coolant Pump[J]. Nuclear Power Engineering, 2023, 44(S2): 126-132. doi: 10.13832/j.jnpe.2023.S2.0126

Citation:

Lyu Tianzhi, Yang Congxin, Guo Yanlei. Research on Hydraulic Performance of LFR Axial-flow Reacter Coolant Pump[J]. Nuclear Power Engineering, 2023, 44(S2): 126-132. doi: 10.13832/j.jnpe.2023.S2.0126

Lyu Tianzhi, Yang Congxin, Guo Yanlei. Research on Hydraulic Performance of LFR Axial-flow Reacter Coolant Pump[J]. Nuclear Power Engineering, 2023, 44(S2): 126-132. doi: 10.13832/j.jnpe.2023.S2.0126

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Research on Hydraulic Performance of LFR Axial-flow Reacter Coolant Pump

doi: 10.13832/j.jnpe.2023.S2.0126

School of Energy and Power Engineering, Lanzhou University of Technology, Lanzhou, 730050, China

Received Date: 2023-07-11
Rev Recd Date: 2023-09-22
Publish Date: 2023-12-30

Abstract

Abstract

In order to master the flow characteristics of lead-bismuth medium in axial-flow reactor coolant pump, the transient numerical calculation of lead-bismuth medium and water medium was carried out by computational fluid dynamics (CFD) method and shear stress transport (SST k-ω) turbulence model, and the energy changes and their laws of the two media in the calculation domain of impeller and guide vane were compared and analyzed. The research results indicate that the change in Reynolds number of the working medium has a significant impact on the hydraulic performance of the axial-flow reactor coolant pump, and the head and efficiency of the coolant pump with lead-bismuth medium are higher than those with water medium. The theoretical head of the coolant pump is basically the same under two different media, but the actual head with LBE medium is 3% higher than that with the water medium, indicating that the difference between the two media is mainly reflected in the flow loss. In the study of the hydraulic loss forms of two media, it was found that the wing loss caused by friction of the coolant pump with LBE medium is smaller than that with water medium, and the boundary layer separation point of LBE medium is significantly delayed. This study can provide some reference for the hydraulic design of the coolant pump of the lead-cooled fast reactor.
- Lead-cooled fast reactor (LFR),
- Hydraulic loss,
- Friction shear stress,
- Turbulent kinetic energy,
- Reynolds number

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References(17)

References

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