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

Korean Nuclear Society (한국원자력학회)
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Development of a Safety Analysis Code for a Supercritical Water Cooled Reactor (SCWR)

  • Yoon, Han-Young (Fluid Engineering Division, Korea Atomic Energy Research Institute) ;
  • Kim, Soo-Hyung (Fluid Engineering Division, Korea Atomic Energy Research Institute) ;
  • Kim, Hee-Cheol (Fluid Engineering Division, Korea Atomic Energy Research Institute) ;
  • Bae, Yoon-Yeong (Fluid Engineering Division, Korea Atomic Energy Research Institute)
  • Published : 2005.10.27
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