Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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CRITICAL HEAT FLUX ENHANCEMENT

  • Chang, Soon-Heung (Department of Nuclear & Quantum Engineering Korea Advanced Institute of Science and Technology) ;
  • Jeong, Yong-Hoon (Department of Nuclear & Quantum Engineering Korea Advanced Institute of Science and Technology) ;
  • Shin, Byung-Soo (Department of Nuclear & Quantum Engineering Korea Advanced Institute of Science and Technology)
  • Published : 2006.12.01
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Abstract

In this paper, works related to enhancement of the CHF are reviewed in terms of fundamental mechanisms and practical applications. Studies on CHF enhancement in forced convection are divided into two categories, CHF enhancement of internal flow in tubes and enhancement of CHF in the nuclear fuel bundle. Methods of enhancing the CHF of internal flows in tubes include enhancement of the swirl flow using twisted tapes, a helical coil, and a grooved surface; promotion of flow mixing using a hypervapotron; altering the characteristics of the heated surface using porous coatings and nano-fluids; and changing the surface tension of the fluid using additives such as surfactants. In the fuel bundle, mixing vanes or wire wrapped rods can be employed to enhance the CHF by changing the flow distributions. These methods can be applied to practical heat exchange systems such as nuclear reactors, fossil boilers, fusion reactors, etc.

Keywords

References

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