Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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HOT CHANNEL ANALYSIS CAPABILITY OF THE BEST-ESTIMATE MULTI-DIMENSIONAL SYSTEM CODE, MARS 3.0

  • JEONG J.-J. (Korea Atomic Energy Research Institute) ;
  • BAE S. W. (Korea Atomic Energy Research Institute) ;
  • HWANG D. H. (Korea Atomic Energy Research Institute) ;
  • LEE W. J. (Korea Atomic Energy Research Institute) ;
  • CHUNG B. D. (Korea Atomic Energy Research Institute)
  • Published : 2005.10.01
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Abstract

The subchannel analysis capability of MARS, a multi-dimensional thermal-hydraulic system code, has been enhanced. In particular, the turbulent mixing and void drift models for the flow-mixing phenomena in rod bundles were improved. Then, the subchannel analysis feature was combined with the existing coupled system thermal-hydraulics (T/H) and 3D reactor kinetics calculation capability of MARS. These features allow for more realistic simulations of both the hot channel behavior and the global system T/H behavior. Using the coupled features of MARS, a coupled analysis of a main steam line break (MSLB) is carried out for demonstration purposes. The results of the calculations are very reasonable and promising.

Keywords

References

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