Proceedings of the Korean Nuclear Society Conference (한국원자력학회:학술대회논문집)

Korean Nuclear Society (한국원자력학회)
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Effects of Split Core Model for Steam Generator Tube Rupture Evaluation

  • Koh, Jae-Hwa (Korea Electric Power Research Institute, Safety Analysis Group) ;
  • Lee, Dong-Hyuk (Korea Electric Power Research Institute, Safety Analysis Group) ;
  • Kim, Yo-Han (Korea Electric Power Research Institute, Safety Analysis Group) ;
  • Sung, Chang-Kyung (Korea Electric Power Research Institute, Safety Analysis Group)
  • Published : 2004.10.28
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