Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Code development and preliminary validation for lead-cooled fast reactor thermal-hydraulic transient behavior

  • Chenglong Wang (Department of Nuclear Science and Technology, State Key Lab. of Multiphase Flow in Power Engineering, Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Xi'an Jiaotong University) ;
  • Chen Wang (Department of Nuclear Science and Technology, State Key Lab. of Multiphase Flow in Power Engineering, Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Xi'an Jiaotong University) ;
  • Wenxi Tian (Department of Nuclear Science and Technology, State Key Lab. of Multiphase Flow in Power Engineering, Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Xi'an Jiaotong University) ;
  • Guanghui Su (Department of Nuclear Science and Technology, State Key Lab. of Multiphase Flow in Power Engineering, Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Xi'an Jiaotong University) ;
  • Suizheng Qiu (Department of Nuclear Science and Technology, State Key Lab. of Multiphase Flow in Power Engineering, Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Xi'an Jiaotong University)
  • Received : 2023.04.10
  • Accepted : 2024.01.28
  • Published : 2024.06.25
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Abstract

Lead-cooled fast reactors (LFRs) have a wide range of application scenarios, which require the thermal-hydraulic characteristics of LFRs to be reliable. In the present paper, the Lead-cooled fast reactor Thermal-Hydraulic Analysis Code LETHAC was developed, including the models of pipe, heat exchanger, and pool. To verify the correctness of LETHAC, two experimental facilities and three experimental cases were selected, including GFT and PLOFA tests for NACIE-UP and Test-1 for CIRCE. The calculated results show the same and consistent trend with the experimental data, but there are some discrepancies. It can be found that LETHAC is suitable and reliable in predicting the transient behavior of lead-cooled system.

Keywords

Acknowledgement

The authors would like to thank the support from Innovative Scientific Program of CNNC.

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