Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Development and validation of wall and interfacial friction models in LOCUST for reactor downcomer with direct vessel injection

  • Rongshuan Xu (China Nuclear Power Technology Research Institute) ;
  • Xinan Wang (China Nuclear Power Technology Research Institute) ;
  • Caihong Xu (China Nuclear Power Technology Research Institute) ;
  • Dongyu He (China Nuclear Power Technology Research Institute) ;
  • Ting Wang (China Nuclear Power Technology Research Institute) ;
  • Jinggang Li (China Nuclear Power Technology Research Institute)
  • Received : 2024.01.14
  • Accepted : 2024.06.02
  • Published : 2024.10.25
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Abstract

The multi-dimensional thermal-hydraulic phenomena in the downcomer of advanced pressurized water reactor with direct vessel injection system are the key points for the safety analysis during a loss of coolant accident. In order to improve the accuracy of LOCUST code for the predictions of thermal-hydraulic phenomena in downcomer region, some newly correlations have been implemented into LOCUST code. The wall friction model of LOCUST code was modified based on the correlations which developed by Yang. The interfacial friction models in LOCUST code have been modified as Hibiki-Ishii correlations. In addition, in order to simulate the upward flow of recirculation flow in downcomer region, the Kinoshita-Hibiki correlations have been also implemented into LOCUST code for better simulating the recirculation flow in downcomer region. The modified code was validated with experimental data of DOBO facility. Five tests of DOBO facility have been calculated by LOCUST, and the calculated axial void fraction distributions have been compared with the measurements. The results show that the modified LOCUST with new correlations of distribution parameter and drift velocity shows better accuracy than the original code. The deviations of the modified LOCUST code are less than the original code and are almost within ±20 %.

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References

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