원전 안전주입배관에서의 열성층 유동해석

Analysis for the Behavior of Thermal Stratification in Safety Injection Piping of Nuclear Power Plant

  • 박만흥 (한국전력기술(주) 전력기술개발연구소) ;
  • 김광추 (한국전력기술(주) 전력기술개발연구소) ;
  • 염학기 (한국전력기술(주) 전력기술개발연구소) ;
  • 김태룡 (한국전력공사 전력연구원) ;
  • 이선기 (한국전력공사 전력연구원) ;
  • 김경훈 (경희대학교 기계공학과)
  • 발행 : 2001.06.27

초록

A numerical analysis has been perfonned to estimate the effect of turbulent penetration and thermal stratified flow in the branch lines piping. This phenomenon of thermal stratification are usually observed in the piping lines of the safety related systems and may be identified as the source of fatigue in the piping system due to the thermal stress loading which are associated with plant operating modes. The turbulent penetration length reaches to $1^{st}$ valve in safety injection piping from reactor coolant system (RCS) at normal operation for nuclear power plant when a coolant does not leak out through valve. At the time, therefore, the thermal stratification does not appear in the piping between RCS piping and $1^{st}$ valve of safety injection piping. When a coolant leak out through the $1^{st}$ valve by any damage, however, the thermal stratification can occur in the safety injection piping. At that time, the maximum temperature difference of fluid between top and bottom in the piping is estimated about $50^{\circ}C$.

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