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Numerical study on two-phase flow instability in multi-parallel channels of helical-coiled once-through steam generator of lead-cooled fast reactor

  • Guan-Hua Qian (School of Nuclear Science and Technology, University of South China) ;
  • Ya-Nan Zhao (School of Nuclear Science and Technology, University of South China) ;
  • Xu Wang (China Nuclear Engineering Consulting Co., Ltd.) ;
  • Peng-Cheng Zhao (School of Nuclear Science and Technology, University of South China) ;
  • Jin-Sen Xie (School of Nuclear Science and Technology, University of South China) ;
  • Tao Yu (School of Nuclear Science and Technology, University of South China)
  • Received : 2023.11.10
  • Accepted : 2024.06.30
  • Published : 2024.11.25

Abstract

The helical-coiled once-through steam generator (H-OTSG) has the advantages of compact structure and strong heat transfer ability, and is appropriate for lead-cooled fast reactor. The two-phase flow instability may cause mechanical vibration and thermal fatigue of heat transfer tube bundles, posing a serious threat to the safe operation of the H-OTSG. In this work, the secondary side of the H-OTSG characterized as multi-parallel channels is modeled by RELAP5/MOD3.4 code, and the oscillation behavior during start-up and the influence of structural and operating parameters on system stability are studied based on time-domain method. The results indicate that the pressure, flow rate, and temperature of the secondary fluid exhibit density wave oscillations at the heating section in a (n-2,2) pattern. In addition, increasing inlet throttling, reducing outlet throttling, controlling subcooling within an appropriate range and avoiding operation under low loads are all beneficial for improving the system stability of the helical-coiled once-through steam generator.

Keywords

Acknowledgement

The authors would like to express their deepest gratitude to NEAL (Nuclear Engineering and Application Laboratory) Team for its help during this research.

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