The Design Optimization of Preventive Measure Against APR1400 Steam Generator Tube Fretting Wear

신형경수로 증기발생기 마모손상 억제를 위한 설계최적화

  • 임혁순 (한수원(주)원자력환경기술원) ;
  • 박영섭 (한수원(주)원자력환경기술원) ;
  • 이광한 (한수원(주)원자력환경기술원) ;
  • 이석호 (한수원(주)원자력환경기술원) ;
  • 정대율 (한수원(주)원자력환경기술원)
  • Published : 2004.04.28

Abstract

Inconel-600 alloy has been used as steam generator tube material for current pressurized water reactors (PWRs). The long-term operation of steam generators showed that the use of this material induced localized corrosion damages and increased tube wear of steam generator. To protect these problems, steam generator tube material is being changed to Inconel-690 alloy. Based on the current trend, we have chosen Inconel 690 as the Advanced Power Reactor 1400 (APR1400) steam generator(SG) tube material and performed the design optimization of preventive measure against tube fretting wear for the APR1400 steam generator. In this paper, we examined the technical consideration in this modification : the selection of material, wear characteristics, effect of the Egg-crate Flow Distribution Plate installation, and effect analysis of vertical strip installation.

Keywords