Nuclear Engineering and Technology

  • 제53권9호
  • /
  • Pages.2839-2846
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  • 2021
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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A preliminary study on material effects of critical heat flux for downward-facing flow boiling

  • Wang, Kai (Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo) ;
  • Li, Chun-Yen (Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo) ;
  • Uesugi, Kotaro (Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo) ;
  • Erkan, Nejdet (Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo) ;
  • Okamoto, Koji (Nuclear Professional School, School of Engineering, The University of Tokyo)
  • 투고 : 2020.05.03
  • 심사 : 2021.03.26
  • 발행 : 2021.09.25
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초록

In this study, experiments of downward-facing flow boiling were conducted to investigate material effects on CHF. Experiments were conducted using aluminum, copper, and carbon steel. It was found that different materials had different CHFs. Aluminum has the biggest CHF while copper has the lowest CHF for each mass flux. After experiment, surface wettability increased and surface became rougher, which was probably due to the oxidation process during nucleate boiling. The CHF difference is likely to be related to the surface wettability, roughness and thermal effusivity, which influences the bubble behavior and in turn affects CHF. Further studies are needed to determine which factor is dominant.

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과제정보

This work was supported by the Japan Grant-in-Aid for Scientific Research (B) (Grand No. 19H02645) and the Ministry of Education, Culture, Sports, Science and Technology of Japan (MEXT) (Grand No. 1081782).

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