Numerical Investigation on Thermal Hydraulics of Helical Coil Tube Once Through Steam Generator for LBE Fast Reactor

Ding Xueyou; Chen Zhiqiang; Wen Qinglong; Ruan Shenhui; Qiao Pengrui

doi:10.13832/j.jnpe.2021.04.0021

Volume 42 Issue 4

Aug. 2021

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Article Navigation > Nuclear Power Engineering > 2021 > 42(4): 21-26

Ding Xueyou, Chen Zhiqiang, Wen Qinglong, Ruan Shenhui, Qiao Pengrui. Numerical Investigation on Thermal Hydraulics of Helical Coil Tube Once Through Steam Generator for LBE Fast Reactor[J]. Nuclear Power Engineering, 2021, 42(4): 21-26. doi: 10.13832/j.jnpe.2021.04.0021

Citation:

Ding Xueyou, Chen Zhiqiang, Wen Qinglong, Ruan Shenhui, Qiao Pengrui. Numerical Investigation on Thermal Hydraulics of Helical Coil Tube Once Through Steam Generator for LBE Fast Reactor[J]. Nuclear Power Engineering, 2021, 42(4): 21-26. doi: 10.13832/j.jnpe.2021.04.0021

Citation:

Ding Xueyou, Chen Zhiqiang, Wen Qinglong, Ruan Shenhui, Qiao Pengrui. Numerical Investigation on Thermal Hydraulics of Helical Coil Tube Once Through Steam Generator for LBE Fast Reactor[J]. Nuclear Power Engineering, 2021, 42(4): 21-26. doi: 10.13832/j.jnpe.2021.04.0021

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Numerical Investigation on Thermal Hydraulics of Helical Coil Tube Once Through Steam Generator for LBE Fast Reactor

doi: 10.13832/j.jnpe.2021.04.0021

1.
Department of Nuclear Engineering, School of Energy and Power Engineering, Chongqing University, Chongqing, 400044, China
2.
Key Laboratory of Low Grade Energy Utilization Technologies and Systems, Chongqing University, Chongqing, 400044, China
3.
China Institute of Atom Energy, Beijing, 102413, China

Received Date: 2020-05-26
Rev Recd Date: 2021-02-26
Publish Date: 2021-08-15

Abstract

Abstract

The design of Lead and Bismuth Eutectic (LBE) cooled fast reactor helical coil tube steam generator is modeled in this study. Physical modeling method is developed with the combination of fine grid blocks and porous medium. Through the coupling the primary three-dimensional turbulence calculation and the secondary side heat transfer based on UDF (User Defined Function) method, a numerical analysis of the thermal hydraulic characteristics of the steam generator is carried out in the FLUENT solver. The results show that: a. the flow distribution holes near LBE inlet and the straight tubes in the chamber have peaks in the flow rate of LBE, and the maximum radial velocity is 0.431 m/s, b. when LBE flows from the inlet chamber into the tube bundle, the pressure, cross flow and axial flow rates change rapidly because of resistance mutation, and c. the changing process of thermal hydraulic parameters confirms to the qualitative mechanism analysis results of flow and heat transfer. The maximum temperature difference between primary and secondary sides near the Critical Heat Flux (CHF) point is 109.61 K, and the maximum heat flux is 323.55 kW/m². This study will provide an important reference for HOTSG structure design, fluid-induced vibration and safety evaluation of lead-bismuth fast reactor.
- LBE fast reactor,
- Helical coil tube once through steam generator,
- Numerical investigation,
- Porous medium,
- Thermal-hydraulics

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References(11)

References

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