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Volume 43 Issue 3
Jun.  2022
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Liu Dalin, Liu Xiaojing, Huang Yanping, Gong Houjun. Numerical Simulation of Lead-bismuth Alloy Solidification in Lead-water Reaction[J]. Nuclear Power Engineering, 2022, 43(3): 7-14. doi: 10.13832/j.jnpe.2022.03.0007
Citation: Liu Dalin, Liu Xiaojing, Huang Yanping, Gong Houjun. Numerical Simulation of Lead-bismuth Alloy Solidification in Lead-water Reaction[J]. Nuclear Power Engineering, 2022, 43(3): 7-14. doi: 10.13832/j.jnpe.2022.03.0007

Numerical Simulation of Lead-bismuth Alloy Solidification in Lead-water Reaction

doi: 10.13832/j.jnpe.2022.03.0007
  • Received Date: 2021-04-06
  • Accepted Date: 2021-11-24
  • Rev Recd Date: 2021-05-18
  • Publish Date: 2022-06-07
  • In order to study the solidification mechanism of lead-bismuth alloy in the reaction between lead-bismuth alloy and water caused by steam generator tube rupture (SGTR), in this paper, by coupling the VOF model, the Realizable k-ε turbulence model, the solidification heat transfer model, and using the FLUENT software, a two-dimensional simulation model of the reaction process of lead-bismuth alloy and water is established, and the model is compared and verified with the results of the existing reaction experiments. Then, based on the enthalpy method, the enthalpy equation of solidification heat transfer characteristics which can directly describe the solidification phenomenon of lead-bismuth alloy is established, the factors and conditions affecting the solidification of lead-bismuth alloy are studied by controlling the model variables. Finally, the model is applied to the scene with complex structure. The results show that the temperature difference between lead-bismuth alloy and water, the initial speed of water jet and the diameter of water injection are the main factors affecting the solidification of lead-bismuth alloy. The model proposed in this paper has high reliability and can simulate the solidification phenomenon of lead-bismuth alloy under actual working conditions. The mechanistic and phenomenological conclusions obtained in this study can provide theoretical support for the safety analysis of lead-based fast reactor.

     

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