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냉각재 상실사고 후 격납건물내의 이상유동 연구

A Study on the Two Phase Flow in the Floor of Containment Building after a Loss of Coolant Accident

  • 배진효 (한국전력기술(주) 전력기술개발연구소) ;
  • 박만흥 (한국전력기술(주) 전력기술개발연구소) ;
  • 고철균 (한양대학교 대학원 기계공학과) ;
  • 이재헌 (한양대학교 공과대학 기계공학과)
  • 투고 : 1999.02.01
  • 발행 : 1999.10.01

초록

The Regulatory Guide 1.82 recommends an analysis of hydraulic performance for sump of ECCS (Emergency Core Cooing System) when LOCA(Loss of Coolant Accident) occurs in a nuclear power plant. The present study deals with 3-dimensional, unsteady, turbulent and two-phase flow simulation to examine the behavior of mixture of reactor coolant and debris near the floor of containment building in conjunction with appropriate assumptions. The dispersed solid model has been adjusted to the interfacial momentum transfer between reactor coolant and debris. According to the results, the counterclockwiserecirculation zone had been formed in the region between sump and connection aisle about 376 second after LOCA occurs. The debris thickness accumulated on a sump screen periodically increases or decreases up to 2000 second, afterwards its peak decreases.

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