Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Thermal-hydraulic study of air-cooled passive decay heat removal system for APR+ under extended station blackout

  • Kim, Do Yun (Korea Advanced Institute of Science & Technology (KAIST), Department of Nuclear and Quantum Engineering) ;
  • NO, Hee Cheon (Korea Advanced Institute of Science & Technology (KAIST), Department of Nuclear and Quantum Engineering) ;
  • Yoon, Ho Joon (Department of Nuclear Engineering, Khalifa University of Science, Technology & Research (KUSTAR)) ;
  • Lim, Sang Gyu (Korea Hydro and Nuclear Power Co.-Central Research Institute)
  • Received : 2018.05.01
  • Accepted : 2018.09.12
  • Published : 2019.02.25
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Abstract

The air-cooled passive decay heat removal system (APDHR) was proposed to provide the ultimate heat sink for non-LOCA accidents. The APDHR is a modified one of Passive Auxiliary Feed-water system (PAFS) installed in APR+. The PAFS has a heat exchanger in the Passive Condensate Cooling Tank (PCCT) and can remove decay heat for 8 h. After that, the heat transfer rate through the PAFS drastically decreases because the heat transfer condition changes from water to air. The APDHR with a vertical heat exchanger in PCCT will be able to remove the decay heat by air if it has sufficient natural convection in PCCT. We conducted the thermal-hydraulic simulation by the MARS code to investigate the behavior of the APR + selected as a reference plant for the simulation. The simulation contains two phases based on water depletion: the early phase and the late phase. In the early phase, the volume of water in PCCT was determined to avoid the water depletion in three days after shutdown. In the late phase, when the number of the HXs is greater than 4089 per PCCT, the MARS simulation confirmed the long-term cooling by air is possible under extended Station Blackout (SBO).

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References

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