Thermal-Hydraulic Analysis Methodology of Nuclear Power Plant Steam Generator

원전 증기발생기 열유동 해석법

  • 최석기 (한국원자력연구소 칼리머기술개발팀) ;
  • 김성오 (한국원자력연구소 칼리머기술개발팀) ;
  • 최훈기 (창원대학교 기계공학과)
  • Published : 2002.06.01

Abstract

This paper presents the numerical methodology of ATHOS3 code for thermal hydraulic analysis of steam generators in nuclear power plant. Topics include porous media approach, governing equations, physical models and correlations for solid-to-fluid interaction and heat transfer, and numerical solution scheme. The ATHOS3 code is applied to the thermal hydraulic analysis of steam generator in the Korea Kori Unit-1 nuclear power plant and the computed results are presented

Keywords

References

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