Thermal-Hydraulic Analysis of Kori Unit-1 Steam Generator Using ATHOS3 Code

ATHOS3 코드에 의한 고리1호기 증기발생기 열유동해석

  • 최석기 (한국원자력연구소 칼리머기술개발팀) ;
  • 남호윤 (한국원자력연구소 칼리머기술개발팀) ;
  • 김의광 (한국원자력연구소 칼리머기술개발팀) ;
  • 김형남 (전력연구원 원전설비지원그룹) ;
  • 장기상 (전력연구원 원전설비지원그룹) ;
  • 홍성열 (전력연구원 원전설비지원그룹)
  • Published : 2001.10.01

Abstract

This paper presents the numerical methodology of ATHOS3 code for thermal hydraulic analysis of Pressurized Water Reactor (PWR) steam generators. 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