Huadian Technology ›› 2016, Vol. 38 ›› Issue (1): 68-71.

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Simulation analysis of small break loss of coolant accident of AP1000 power unit

  

  1. North China Electric Power University,a.Institute of Nuclear Thermal hydraulic Safety and Standardization; b. Beijing Key Laboratory for Passive Safety Technology of Nuclear Energy,Beijing 102206,China
  • Online:2016-01-25 Published:2016-03-15

Abstract:

Abstract:Using the nuclear accident simulation software PCTRAN of MST Company, this paper carried out a transient curve analysis of small break loss of coolant accident (SBLOCA) of AP1000 power unit.The simulation results are as follows:After the occurrence of 400 cm2 SBLOCA of AP1000 power unit,the water levels of makeup tank and safety injection tank of reactor core fall with the pressure decrease of reactor system. When the pressure drops to 13.09 MPa,the heat exchanger of passive residual heat removal system is triggered to remove the residual heat of reactor core.When the pressure continues to drop to  1.52 MPa,the water level of reactor core begins to rise.After the pressure reaches to 0.29MPa,it begins to be stabilizing.The calculated system pressure is in concordance with the results that obtained using the software NOTRUMP by Westinghouse Corporation in time and number.

Key words: Keywords:AP1000 power unit, small break loss of coolant accident, PCTRAN, transient curve, simulation analysis