Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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PREDICTION OF THE REACTOR VESSEL WATER LEVEL USING FUZZY NEURAL NETWORKS IN SEVERE ACCIDENT CIRCUMSTANCES OF NPPS

  • Park, Soon Ho (Department of Nuclear Engineering, Chosun University) ;
  • Kim, Dae Seop (Department of Nuclear Engineering, Chosun University) ;
  • Kim, Jae Hwan (Department of Nuclear Engineering, Chosun University) ;
  • Na, Man Gyun (Department of Nuclear Engineering, Chosun University)
  • Received : 2013.10.04
  • Accepted : 2013.12.24
  • Published : 2014.06.25
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Abstract

Safety-related parameters are very important for confirming the status of a nuclear power plant. In particular, the reactor vessel water level has a direct impact on the safety fortress by confirming reactor core cooling. In this study, the reactor vessel water level under the condition of a severe accident, where the water level could not be measured, was predicted using a fuzzy neural network (FNN). The prediction model was developed using training data, and validated using independent test data. The data was generated from simulations of the optimized power reactor 1000 (OPR1000) using MAAP4 code. The informative data for training the FNN model was selected using the subtractive clustering method. The prediction performance of the reactor vessel water level was quite satisfactory, but a few large errors were occasionally observed. To check the effect of instrument errors, the prediction model was verified using data containing artificially added errors. The developed FNN model was sufficiently accurate to be used to predict the reactor vessel water level in severe accident situations where the integrity of the reactor vessel water level sensor is compromised. Furthermore, if the developed FNN model can be optimized using a variety of data, it should be possible to predict the reactor vessel water level precisely.

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References

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