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

Korean Nuclear Society (한국원자력학회)
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Parameter Study for the Feedwater Pipe Break Analysis of an Integral Type Reactor

  • Chung, Young-Jong (Fluid System Engineering Division, Korea Atomic Energy Research Institute) ;
  • Kim, Soo-Hyung (Fluid System Engineering Division, Korea Atomic Energy Research Institute) ;
  • Kim, Hee-Cheol (Fluid System Engineering Division, Korea Atomic Energy Research Institute) ;
  • Zee, Sung-Quun (Reactor Engineering Division, Korea Atomic Energy Research Institute)
  • Published : 2005.10.27
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