Estimation of the Nuclear Power Peaking Factor Using In-core Sensor Signals

The local power density should be estimated accurately to prevent fuel rod melting. The local power density at the hottest part of a hot fuel rod, which is described by the power peaking factor, is more important information than the local power density at any other position in a reactor core. Therefore, in this work, the power peaking factor, which is defined as the highest local power density to the average power density in a reactor core, is estimated by fuzzy neural networks using numerous measured signals of the reactor coolant system. The fuzzy neural networks are trained using a training data set and are verified with another test data set. They are then applied to the first fuel cycle of Yonggwang nuclear power plant unit 3. The estimation accuracy of the power peaking factor is 0.45% based on the relative 2σerror by using the fuzzy neural networks without the in-core neutron flux sensors signals input. A value of 0.23% is obtained with the in-core neutron flux sensors signals, which is sufficiently accurate for use in local power density monitoring.

[1]  Jung-Kun Lee,et al.  Modelling of core protection and monitoring system for PWR nuclear power plant simulator , 1998 .

[2]  Hee-Cheol Kim,et al.  Development of a back propagation network for one-step transient DNBR calculations , 1997 .

[3]  Dong-Ju Lee,et al.  Evaluation of Nuclear Plant Cable Aging Through Condition Monitoring , 2004 .

[4]  Wang Kee In,et al.  Assessment of core protection and monitoring systems for an advanced reactor SMART , 2002 .

[5]  Jyh-Shing Roger Jang,et al.  ANFIS: adaptive-network-based fuzzy inference system , 1993, IEEE Trans. Syst. Man Cybern..

[6]  Man Gyun Na Application of a genetic neuro-fuzzy logic to departure from nucleate boiling protection limit estimation , 1999 .

[7]  Poong Hyun Seong,et al.  A methodology for benefit assessment of using in-core neutron detector signals in core protection calculator system (CPCS) for Korea standard nuclear power plants (KSNPP) , 1999 .

[8]  Man Gyun Na,et al.  DNB limit estimation using an adaptive fuzzy inference system , 1999, 1999 IEEE Nuclear Science Symposium. Conference Record. 1999 Nuclear Science Symposium and Medical Imaging Conference (Cat. No.99CH37019).

[9]  Soon Heung Chang,et al.  Improved methodology for generation of axial flux shapes in digital core protection systems , 2002 .

[10]  Michio Sugeno,et al.  Fuzzy identification of systems and its applications to modeling and control , 1985, IEEE Transactions on Systems, Man, and Cybernetics.

[11]  Myeong-Gie Kang Effects of Pool Subcooling on Boiling Heat Transfer in a Annulus , 2004 .