Journal of computational fluids engineering (한국전산유체공학회지)

Korean Society of Computational Fluids Engineering (한국전산유체공학회)
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THE IMPLEMENTATION OF BORON TRANSPORT EQUATION INTO A REACTOR COMPONENT ANLAYSIS CODE

원자로 기기 열수력 해석 코드에서 붕소 수송 방정식의 구현

  • Park, Ik Kyu (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Lee, Seung Wook (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Yoon, Han Young (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute)
  • 박익규 (한국원자력연구원 열수력안전연구부) ;
  • 이승욱 (한국원자력연구원 열수력안전연구부) ;
  • 윤한영 (한국원자력연구원 열수력안전연구부)
  • Received : 2013.08.14
  • Accepted : 2013.11.04
  • Published : 2013.12.31
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Abstract

The boron transport model has been implemented into the CUPID code to simulate the boron transport phenomena of the PWR. The boron concentration conservation was confirmed through a simulation of a conceptual boron transport problem in which water with a constant inlet boron concentration injected into an inlet of the 2-dimensional vertical flow tube. The step wise boron transport problem showed that the numerical diffusion of the boron concentration can be reduced by the second order convection scheme. In order to assess the adaptability of the developed boron transport model to the realistic situation, the ROCOM test was simulated by using the CUPID implemented with the boron transportation.

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References

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