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Volume 44 Issue 3
Jun.  2023
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Liu Jialun, Li Huixiong, Zhang Shunzhe, Ning Liang, Tang Linghong. Analysis on Thermal Hydraulic Characteristic of Helical Coiled Tube Steam Generator of Liquid Metal Fast Reactor Based on Drift-Flux Model[J]. Nuclear Power Engineering, 2023, 44(3): 79-89. doi: 10.13832/j.jnpe.2023.03.0079
Citation: Liu Jialun, Li Huixiong, Zhang Shunzhe, Ning Liang, Tang Linghong. Analysis on Thermal Hydraulic Characteristic of Helical Coiled Tube Steam Generator of Liquid Metal Fast Reactor Based on Drift-Flux Model[J]. Nuclear Power Engineering, 2023, 44(3): 79-89. doi: 10.13832/j.jnpe.2023.03.0079

Analysis on Thermal Hydraulic Characteristic of Helical Coiled Tube Steam Generator of Liquid Metal Fast Reactor Based on Drift-Flux Model

doi: 10.13832/j.jnpe.2023.03.0079
  • Received Date: 2022-07-09
  • Rev Recd Date: 2022-08-17
  • Publish Date: 2023-06-15
  • In the helical coiled tube steam generator of liquid metal fast reactor, the temperature difference between inlet and outlet of the primary side increases significantly, and the outlet steam superheat degree of the secondary side also increases significantly. This is a common problem and brings new challenges to the safe operation of steam generator. Based on the discrete grid method, a computational model suitable for the thermal-hydraulic characteristics of the helical coiled tube steam generator of the liquid metal fast reactor was established. The model meshed both the primary side circuit and the secondary side circuit. The drift-flux method was adopted to calculate the flux and heat transfer process of two-phase steam-water flow along the helical coiled tube, and the correlations of liquid metal physical properties and liquid metal heat transfer were selected for the primary side calculation. Meanwhile, the inner node method was adopted to divide the tube wall into a series of grids, and the heat conduction equations were built to accurately simulate the convective heat transfer between the fluid on both sides and the tube wall, as well as the wall metal heat conduction process. The present model was then verified based on the experimental data. Finally, taking the lead-bismuth fast reactor as an example, the thermal-hydraulic characteristics of the helical coiled tube steam generator were analyzed under different inlet conditions. It was found that the wall heat flux distribution between the primary and secondary sides is extremely uneven along the helical coiled tube steam generator, and the peak wall heat flux is extremely high. The maximum value of the wall heat flux reaches 1,361 kW/m2, and the difference between the maximum value and the minimum value is tens to hundreds of times in the example of this paper. With the increase of lead-bismuth temperature and velocity at the inlet of primary side, the lengths of the subcooled water zone and the two-phase zone on the secondary side are significantly shortened, and the length of the superheated steam zone is significantly increased. Meanwhile, the peak wall heat flux moves towards the inlet of the helical coiled tube, and the total pressure drop of the working medium on the secondary side also increases significantly.

     

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