• HONG, SEONG-WAN (Division of Severe Accident & PHWR Safety Research, Korea Atomic Energy Research Institute) ;
  • KIM, JONGTAE (Division of Severe Accident & PHWR Safety Research, Korea Atomic Energy Research Institute) ;
  • KANG, HYUNG-SEOK (Division of Severe Accident & PHWR Safety Research, Korea Atomic Energy Research Institute) ;
  • NA, YOUNG-SU (Division of Severe Accident & PHWR Safety Research, Korea Atomic Energy Research Institute) ;
  • SONG, JINHO (Division of Severe Accident & PHWR Safety Research, Korea Atomic Energy Research Institute)
  • Received : 2014.12.12
  • Accepted : 2014.12.22
  • Published : 2015.02.25


During the past 10 years, the Korea Atomic Energy Research Institute (KAERI) has performed a study to control hydrogen gas in the containment of the nuclear power plants. Before the Fukushima accident, analytical activities for gas distribution analysis in experiments and plants were primarily conducted using a multidimensional code: the GASFLOW. After the Fukushima accident, the COM3D code, which can simulate a multidimensional hydrogen explosion, was introduced in 2013 to complete the multidimensional hydrogen analysis system. The code validation efforts of the multidimensional codes of the GASFLOW and the COM3D have continued to increase confidence in the use of codes using several international experimental data. The OpenFOAM has been preliminarily evaluated for APR1400 containment, based on experience from coded validation and the analysis of hydrogen distribution and explosion using the multidimensional codes, the GASFLOW and the COM3D. Hydrogen safety in nuclear power has become a much more important issue after the Fukushima event in which hydrogen explosions occurred. The KAERI is preparing a large-scale test that can be used to validate the performance of domestic passive autocatalytic recombiners (PARs) and can provide data for the validation of the severe accident code being developed in Korea.


Supported by : National Research Foundation of Korea


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