Nuclear Engineering and Technology

  • 제56권7호
  • /
  • Pages.2474-2479
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  • 2024
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Enhancement of critical heat flux with additive-manufactured heat-transfer surface

  • Tatsuya Kano (Cooperative Major in Nuclear Energy, Graduate School of Advanced Science and Engineering, Waseda University) ;
  • Rintaro Ono (Cooperative Major in Nuclear Energy, Graduate School of Advanced Science and Engineering, Waseda University) ;
  • Masahiro Furuya (Cooperative Major in Nuclear Energy, Graduate School of Advanced Science and Engineering, Waseda University)
  • 투고 : 2023.10.24
  • 심사 : 2024.02.03
  • 발행 : 2024.07.25
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초록

In-Vessel Retention (IVR) is a key technology to retain the molten core in the reactor vessel during severe accidents of Pressurized-water reactors (PWRs). In order to gain the safety margin of IVR, it is crucial to enhance the critical heat flux (CHF) of the reactor vessel, which is submerged in a water pool. To enhance the CHF, we have designed and additive-manufactured porous grid plates with a 3-D printer for design flexibility. We measured the CHF for the porous grid plate on the boiling heat transfer surface and found that the CHF was enhanced by 50 % more than that of the bare surface. The CHF enhanced more with a narrower grid pitch and a lower grid height. The visual observation study revealed that the vapor film was formed at the bottom of the grid plate.

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과제정보

This work was supported by JSPS KAKENHI Grant Number JP21421713.

참고문헌

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