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http://dx.doi.org/10.5516/NET.2009.41.9.1181

ESTIMATION OF THE POWER PEAKING FACTOR IN A NUCLEAR REACTOR USING SUPPORT VECTOR MACHINES AND UNCERTAINTY ANALYSIS  

Bae, In-Ho (Department of Nuclear Engineering, Chosun University)
Na, Man-Gyun (Department of Nuclear Engineering, Chosun University)
Lee, Yoon-Joon (Cheju National University)
Park, Goon-Cherl (Seoul National University)
Publication Information
Nuclear Engineering and Technology / v.41, no.9, 2009 , pp. 1181-1190 More about this Journal
Abstract
Knowing more about the Local Power Density (LPD) at the hottest part of a nuclear reactor core can provide more important information than knowledge of the LPD at any other position. The LPD at the hottest part needs to be estimated accurately in order to prevent the fuel rod from melting in a nuclear reactor. Support Vector Machines (SVMs) have successfully been applied in classification and regression problems. Therefore, in this paper, the power peaking factor, which is defined as the highest LPD to the average power density in a reactor core, was estimated by SVMs which use numerous measured signals of the reactor coolant system. The SVM models were developed by using a training data set and validated by an independent test data set. The SVM models' uncertainty was analyzed by using 100 sampled training data sets and verification data sets. The prediction intervals were very small, which means that the predicted values were very accurate. The predicted values were then applied to the first fuel cycle of the Yonggwang Nuclear Power Plant Unit 3. The root mean squared error was approximately 0.15%, which is accurate enough for use in LPD monitoring and for core protection that uses LPD estimation.
Keywords
Local Power Density; Power Peaking Factor; Subtractive Clustering; Support Vector Machine;
Citations & Related Records
Times Cited By KSCI : 3  (Citation Analysis)
Times Cited By Web Of Science : 1  (Related Records In Web of Science)
Times Cited By SCOPUS : 1
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1 G.Y. Heo, "Condition monitoring using empirical models: technical review and prospects for nuclear applications," Nucl. Eng. Tech., vol. 40, pp. 49-68, Feb. 2008   과학기술학회마을   DOI
2 W.K. In, D.H. Hwang, Y.J. Yoo, and S.Q. Zee, “Assessment of core protection and monitoring systems for an advanced reactor SMART,” Annals of Nuclear Energy, vol. 29, no. 5, pp. 609-621, Mar. 2002   DOI   ScienceOn
3 I.H. Bae, M.G. Na, Y.J. Lee, and G.C. Park, “Calculation of the power peaking factor in a nuclear reactor using support vector regression models,” Annals of Nuclear Energy, vol. 35, no. 12, pp. 2200-2205, Dec. 2008   DOI   ScienceOn
4 V. Vapnik, The Nature of Statistical Learning Theory. New York: Springer, 1995
5 G.C. Lee, W.P. Baek, and S.H. Chang, “Improved methodology for generation of axial flux shapes in digital core protection systems,” Annals of Nuclear Energy, vol. 29, no. 7, pp. 805-819, May 2002   DOI   ScienceOn
6 M G. Na, “Application of a genetic neuro-fuzzy logic to departure from nucleate boiling protection limit estimation,” Nuclear Technology, vol. 128, pp. 327-340, Apr. 1999   DOI
7 V. Kecman, Learning and Soft Computing. Cambridge, Massachusetts: MIT Press, 2001
8 ABB Combustion Engineering Inc., “Overview Description of the Core Operation Limit Supervisory System (COLSS),” CEN-312-P, Revision 01-P, 1986
9 S.R. Gunn, Support Vector Machines for Classification and Regression. Technical Report, University of Southampton, 1998
10 M.G. Na, D.W. Jung, S.H. Shin, K.B. Lee, and Y.J. Lee, “Estimation of the nuclear power peaking factor using incore sensor signals,” Nucl. Eng. Tech., vol. 36, no. 5, pp. 420-429, Oct. 2004
11 V. N. Vapnik, Statistical Learning Theory. New York, NY: John Wiley & Sons, 1998
12 J. Garvey, D. Garvey, R. Seibert, J.W. Hines, “Validation of on-line monitoring techniques to nuclear plant data,” Nucl. Eng. Tech., vol. 39, no. 2, pp. 149-158, Apr. 2007   DOI
13 H.C. Kim and S.H. Chang, “Development of a back propagation network for one-step transient DNBR calculations,” Annals of Nuclear Energy, vol. 24, no. 17, pp.1437-1446, Nov. 1997   DOI   ScienceOn
14 S.Han, U.S. Kim, and P.H. Seong, “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),” Annals of Nuclear Energy, vol. 26, no. 6, pp. 471-488, 1999   DOI   ScienceOn
15 B.O. Cho, H.G. Joo, J.Y. Cho, S.Q. Zee, “MASTER: reactor core design and analysis code,” Proceedings of 2002 Int. Conf. New Frontiers of Nuclear Technology: Reactor Physics (PHYSOR 2002), Seoul, Korea, Oct. 7-10, 2002
16 M. G. Na, “DNB limit estimation using an adaptive fuzzy inference system,” IEEE Trans. Nucl. Sci., vol. 47, no. 6, pp. 1948-1953, Dec. 2000   DOI   ScienceOn
17 S.L. Chiu, “Fuzzy model identification based on cluster estimation,” J. Intell. Fuzzy Systems, vol. 2, pp. 267-278, 1994   DOI   ScienceOn
18 M.G. Na, I.J. Hwang, and Y.J. Lee, “Inferential sensing and monitoring for feedwater flowrate in pressurized water reactors,” IEEE Trans. Nucl. Sci., vol. 53, no. 4, pp. 2335-2342, Aug. 2006   DOI   ScienceOn
19 J.K. Lee and B.S. Han, “Modeling of core protection and monitoring system for PWR nuclear power plant simulator,” Annals of Nuclear Energy, vol. 25, no. 7, pp. 409-420, May 1998   DOI   ScienceOn
20 R. Tibshirani, “A comparison of some error estimates for neural network models,” Neural Computation, vol. 8, pp. 152-163, 1996   DOI
21 J.W. Hines, B. Rasmussen, “Online sensor calibration monitoring uncertainty estimation,” Nuclear Technology, vol. 151, pp. 281-288, Sept. 2005   DOI