Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Improvement of the critical heat flux correlation in a thermal-hydraulic system code for a downward-flow narrow rectangular channel

  • Wisudhaputra, Adnan (School of Mechanical Engineering, Pusan National University) ;
  • Yun, Byong Jo (School of Mechanical Engineering, Pusan National University) ;
  • Jeong, Jae Jun (School of Mechanical Engineering, Pusan National University)
  • Received : 2022.02.28
  • Accepted : 2022.05.21
  • Published : 2022.10.25
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Abstract

Several critical heat flux (CHF) correlations including the look-up table in the MARS code have been assessed for the prediction of CHF in a downward-flow narrow rectangular channel. For the assessment, we built an experiment database that covers pressures between 1.01 and 39.0 bar, gap sizes between 1.09 and 6.53 mm, mass fluxes up to 25,772 kg/m2s, and under one-sided and two-sided heating conditions. The results of the assessment showed that the Kaminaga correlation has the best overall prediction compared to others. However, because the correlation uses global variables, such as inlet and outlet subcooling and total heat transfer area, it is difficult to use in a system code. A new CHF correlation is then proposed by replacing the global variables in the Kaminaga correlation with local ones and adding correction factors to consider the effect of gap size, mass flux, and the number of heating walls. Additional correction factor is added to consider the effect of inlet subcooling. It is shown that the new one is better than the Kaminaga correlation and it is easy to implement to any system code.

Keywords

Acknowledgement

This research was supported by the National Research Foundation (NRF) grant funded by the Ministry of Science, and ICT of the Korean government (Grant code 2019M2D2A1A03056998).

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