Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Identification of hydrogen flammability in steam generator compartment of OPR1000 using MELCOR and CFX codes

  • Jeon, Joongoo (Department of Nuclear Engineering, Hanyang University) ;
  • Kim, Yeon Soo (Department of Nuclear Engineering, Hanyang University) ;
  • Choi, Wonjun (Department of Nuclear Engineering, Hanyang University) ;
  • Kim, Sung Joong (Department of Nuclear Engineering, Hanyang University)
  • Received : 2018.11.08
  • Accepted : 2019.06.23
  • Published : 2019.12.25
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Abstract

The MELCOR code useful for a plant-specific hydrogen risk analysis has inevitable limitations in prediction of a turbulent flow of a hydrogen mixture. To investigate the accuracy of the hydrogen risk analysis by the MELCOR code, results for the turbulent gas behavior at pipe rupture accident were compared with CFX results which were verified by the American National Standard Institute (ANSI) model. The postulated accident scenario was selected to be surge line failure induced by station blackout of an Optimized Power Reactor 1000 MWe (OPR1000). When the surge line failure occurred, the flow out of the surgeline was strongly turbulent, from which the MELCOR code predicted that a substantial amount of hydrogen could be released. Nevertheless, the results indicated nonflammable mixtures owing to the high steam concentration released before the failure. On the other hand, the CFX code solving the three-dimensional fluid dynamics by incorporating the turbulence closure model predicted that the flammable area continuously existed at the jet interface even in the rising hydrogen mixtures. In conclusion, this study confirmed that the MELCOR code, which has limitations in turbulence analysis, could underestimate the existence of local combustible gas at pipe rupture accident. This clear comparison between two codes can contribute to establishing a guideline for computational hydrogen risk analysis.

Keywords

References

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