Finite Element Analysis of PSC Reactor Containment Vessels

프리스트레스트 콘크리트 원자로 격납고의 유한요소해석

  • 송하원 (연세대학교 사회환경시스템공학부) ;
  • 최강룡 (한국원자력안전기술원 책임연구원, 연세대학교) ;
  • 김경단 (VAL KOREA 기술연구소 연구원, 연세대학교) ;
  • 변근주 (연세대학교 사회환경시스템공학부)
  • Published : 2002.04.01

Abstract

In this palter, a finite element technique is applied to both reinforced concrete and prestressed concrete containment vessels to predict the ultimate pressure capacity of the vessels subjected to internal pressure due to accident. The so-called volume-control technique is utilized to control the change in volume enclosed by the cylindrical containment vessels and layered shell elements equipped with a pressure node is utilizing to model the PSC vessels. The finite element analysis is carried out to obtain both global and local failure behavior of prestressed concrete nuclear containment vessels. nalytical results are verified by comparison with experimental data.

Keywords