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학술저널
저자정보
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제46권 제3호
발행연도
2014.1
수록면
373 - 380 (8page)

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Safety-related parameters are very important for confirming the status of a nuclear power plant. In particular, the reactorvessel water level has a direct impact on the safety fortress by confirming reactor core cooling. In this study, the reactor vesselwater level under the condition of a severe accident, where the water level could not be measured, was predicted using a fuzzyneural 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. Theinformative data for training the FNN model was selected using the subtractive clustering method. The prediction performanceof the reactor vessel water level was quite satisfactory, but a few large errors were occasionally observed. To check the effectof instrument errors, the prediction model was verified using data containing artificially added errors. The developed FNNmodel was sufficiently accurate to be used to predict the reactor vessel water level in severe accident situations where theintegrity of the reactor vessel water level sensor is compromised. Furthermore, if the developed FNN model can be optimizedusing a variety of data, it should be possible to predict the reactor vessel water level precisely.

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