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

Korean Nuclear Society (한국원자력학회)
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Overview of Critical Flow Test Program for the Simulation of Loss of Coolant Accident and Preliminary Analysis of Test Results

  • Park, C.K. (Korea Atomic Energy Research Institute (KAERI)) ;
  • Park, H.S. (Korea Atomic Energy Research Institute (KAERI)) ;
  • Yoon, Y.J. (Korea Atomic Energy Research Institute (KAERI)) ;
  • Song, C.H. (Korea Atomic Energy Research Institute (KAERI))
  • Published : 2005.05.26
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