Technical Evaluation of Corium Cooling at the Reactor Cavity

  • Yang, Soo-Hyung (Department of Nuclear Engineering, Korea Advanced Institute of Science and Technology) ;
  • Chang, Keun-Sun (Department of mechanical Engineering, Sunmoon University) ;
  • Lee, Jae-Hun (Korea Institute of nuclear Safety) ;
  • Lee, Jong-In (Korea Institute of nuclear Safety)
  • Published : 1998.05.01

Abstract

To terminate the progression of the sever accident and mitigate the accident consequences, corium coaling has been suggested as one of most important design features considered in the swore accident mitigation. Till now, some kinds of cooling methodologies have been identified and, specially the corium cooling at the reactor cavity has been considered as one of the most promising cooling methodologies. Moreover, several design requirements related to the cerium cooling at the reactor cavity have been also suggested and applied to the design of the next generation reactor. In this study technical description are briefly described for the important issues related to the cerium cooling at the reactor cavity, i.e. cavity area, cavity flooding system, etc., and simple evaluation for those items have been performed considering present technical levels the experiment and analytical works..

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