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http://dx.doi.org/10.5516/NET.04.2012.512

MONITORING SEVERE ACCIDENTS USING AI TECHNIQUES  

No, Young-Gyu (Korea Atomic Energy Research Institute)
Kim, Ju-Hyun (Department of Nuclear Engineering, Chosun University)
Na, Man-Gyun (Department of Nuclear Engineering, Chosun University)
Lim, Dong-Hyuk (Korea Institute of Nuclear Nonproliferation and Control)
Ahn, Kwang-Il (Korea Atomic Energy Research Institute)
Publication Information
Nuclear Engineering and Technology / v.44, no.4, 2012 , pp. 393-404 More about this Journal
Abstract
After the Fukushima nuclear accident in 2011, there has been increasing concern regarding severe accidents in nuclear facilities. Severe accident scenarios are difficult for operators to monitor and identify. Therefore, accurate prediction of a severe accident is important in order to manage it appropriately in the unfavorable conditions. In this study, artificial intelligence (AI) techniques, such as support vector classification (SVC), probabilistic neural network (PNN), group method of data handling (GMDH), and fuzzy neural network (FNN), were used to monitor the major transient scenarios of a severe accident caused by three different initiating events, the hot-leg loss of coolant accident (LOCA), the cold-leg LOCA, and the steam generator tube rupture in pressurized water reactors (PWRs). The SVC and PNN models were used for the event classification. The GMDH and FNN models were employed to accurately predict the important timing representing severe accident scenarios. In addition, in order to verify the proposed algorithm, data from a number of numerical simulations were required in order to train the AI techniques due to the shortage of real LOCA data. The data was acquired by performing simulations using the MAAP4 code. The prediction accuracy of the three types of initiating events was sufficiently high to predict severe accident scenarios. Therefore, the AI techniques can be applied successfully in the identification and monitoring of severe accident scenarios in real PWRs.
Keywords
Artificial Intelligence; Severe Accident; GMDH; FNN; MAAP4 Code;
Citations & Related Records
Times Cited By KSCI : 3  (Citation Analysis)
Times Cited By Web Of Science : 1  (Related Records In Web of Science)
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1 P. B. Ferreira and B. R. Upadhyaya, Incipient Fault Detection and Isolation of Sensors and Field Devices, Nuclear Engineering Dept., Univ. Tennessee, Knoxville, UTNE/BRU/99-02, December 1999.
2 A. G. Ivakhnenko, "Polynomial theory of complex systems", IEEE Trans. Syst. Man & Cybern, SMC-1, pp. 364-378, 1971   DOI
3 S. L. Chiu, "Fuzzy model identification based on cluster estimation," J. Intell. Fuzzy Systems, vol. 2, pp. 267-278, 1994   DOI   ScienceOn
4 Jang, J.-S. R., "ANFIS: Adaptive-network-based fuzzy inference systems," IEEE Transactions on Systems, Man, and Cybernetics, vol. 23, pp. 665-685, 1993.   DOI   ScienceOn
5 Mamdani, E.H. and Assilian, S., "An experiment in linguistic synthesis with a fuzzy logic controller," Int. J. Man-Machine Studies, vol. 7, pp. 1-13, 1975.   DOI   ScienceOn
6 Takagi, T. and Sugeno, M., "Fuzzy identification of systems and its applications to modeling and control," IEEE Trans. System, Man, Cybern., vol. 1, pp. 116-132, 1985.
7 I.-Y.Seo, B.-N. Ha, S.-W. Lee, C.-H. Shin, and S.-J. Kim, "Principal components based support vector regression model for on-line instrument calibration monitoring in NPPs," Nucl. Eng. Technol., vol. 42, no. 2, pp. 219-230, Apr. 2010.   DOI
8 E. Zio and R. Bazzo, "Optimization of the test intervals of a nuclear safety system by genetic algorithms, solution clustering and fuzzy preference assignment," Nucl. Eng. Technol., vol. 42, no. 4, pp. 414-425, Aug. 2010.   DOI
9 R. E. Henry et al., MAAP4 - Modular Accident Analysis Program for LWR Power Plants, User's Manual. Burr Ridge, IL: Fauske, vol. 1-4, 1990.
10 B.-S. Yang, W.-W. Hwang, M.-H. Ko, and S.-J. Lee, "Cavitation detection of butterfly valve using support vector machines," J. Sound Vibr., vol. 287, nos. 1-2, pp. 25-43, Oct. 2005.   DOI
11 D. F. Specht, "Probabilistic neural networks," Neural Networks, vol.3, no. 1, pp. 109-118, 1990.   DOI   ScienceOn
12 A. G. Ivakhnenko, "The group method of data handling; a rival of method of stochastic approximation," Soviet Automatic Control, vol. 1, no. 3, pp. 43-55, 1968.
13 M. C. Acock and Y. A. Pachepsky, "Estimating missing weather data for agricultural simulations using group method of data handling," J. Applied Meteorology, vol. 39, no. 7, pp. 1176-1184, 2000.   DOI   ScienceOn
14 T. Kondo, A. S. Pandya, "GMDH-type neural network algorithm with sigmoid function," Intl. J. Knowledge-Based Engineering Systems, vol. 7, no. 4, pp. 198-205, 2003.
15 S. J. Farlow, Self-Organizing Methods in Modeling: GMDH Type Algorithms. Marcel Dekker, New York, 1984.
16 C. R. Hild, "Development of The Group Method of Data Handling With Information-based Model Evaluation Criteria: A New Approach to Statistical Modeling," Ph.D. Dissertation, Univ. Tennessee, Knoxville, 1998.
17 Y. Bartal, J. Lin, and R. E. Uhrig, "Nuclear power plant transient diagnostics using artificial neural networks that allow "don't-know" classifications," Nucl. Technol., vol. 110, no. 3, pp. 436-449, June 1995.   DOI
18 K. Nabeshima, T. Suzudo, T. Ohno, K. Kudo, "Nuclear reactor monitoring with the combination of neural network and expert system," Mathematics and Computers in Simulation, vol. 60, pp. 233-244, 2002.   DOI
19 Antonio C.A. Mol, et al., "Neural and genetic-based approaches to nuclear transient identification including 'don't know' response," Progress in Nuclear Energy, vol. 48, pp. 268-282, 2006.   DOI   ScienceOn
20 M. G. Na, S. M. Lee, S. H. Shin, D. W. Jung, S. P. Kim, J. H. Jeong, and B. C. Lee, "Prediction of major transient scenarios for severe accidents of nuclear power plants," IEEE Trans. Nucl. Sci., vol. 51, no. 2, pp. 313-321, April 2004.   DOI   ScienceOn
21 T.V. Santosh, et al., "Diagnostic system for identification of accident scenarios in nuclear power plants using artificial neural networks," Reliability Engineering and System Safety, vol. 94, pp. 759-762, 2009.   DOI
22 M. G. Na, W. S. Park, and D. H. Lim, "Detection and diagnostics of loss of coolant accidents using support vector machines," IEEE Trans. Nucl. Sci., vol. 55, no. 1, pp. 628-636, Feb. 2008.   DOI   ScienceOn
23 S. H. Lee, Y. G. No, M. G. Na, K.-I. Ahn and S.-Y. Park, "Diagnostics of loss of coolant accidents using SVC and GMDH models," IEEE Trans. Nucl. Sci., vol. 58, no. 1, pp. 267-276, Feb. 2011.   DOI   ScienceOn
24 Paolo F. Fantoni, "Experiences and applications of PEANO for online monitoring in power plants," Progress in Nucl. Energy, vol. 46, pp. 206-225, 2005.   DOI   ScienceOn
25 Jamie Garvey, Dustin Garvey, Rebecca Seibert and J. Wesley Hines, "Validation of on-line monitoring techniques to nuclear plant data," Nucl. Eng. Technol., vol. 39 no. 2 pp. 149-158, 2007   DOI
26 S. W. Cheon and S. H. Chang, "Application of neural networks to a connectionist expert system for transient identification in nuclear power plants," Nucl. Technol., vol. 102, no. 2, pp. 177-191, May 1993.   DOI
27 Akio Gofuku, Hidekazu Yoshikawa, Shunsuke Hayashi, Kenji Shimizu, Jiro Wakabayashi, "Diagnostic techniques of a small-break loss-of-coolant accident at a pressurized water reactor plant," Nucl. Technol., vol. 81, pp. 313-332, 1988.   DOI