Browse > Article
http://dx.doi.org/10.5516/NET.2011.43.3.301

DIAMETRAL CREEP PREDICTION OF THE PRESSURE TUBES IN CANDU REACTORS USING A BUNDLE POSITION-WISE LINEAR MODEL  

Lee, Sung-Han (Department of Nuclear Engineering, Chosun University)
Kim, Dong-Su (Department of Nuclear Engineering, Chosun University)
Lee, Sim-Won (Department of Nuclear Engineering, Chosun University)
No, Young-Gyu (Department of Nuclear Engineering, Chosun University)
Na, Man-Gyun (Department of Nuclear Engineering, Chosun University)
Lee, Jae-Yong (Korea Electric Power Research Institute)
Kim, Dong-Hoon (Department of Nuclear and Quantum Engineering, KAIST)
Jang, Chang-Heui (Department of Nuclear and Quantum Engineering, KAIST)
Publication Information
Nuclear Engineering and Technology / v.43, no.3, 2011 , pp. 301-308 More about this Journal
Abstract
The diametral creep of pressure tubes (PTs) in CANDU (CANada Deuterium Uranium) reactors is one of the principal aging mechanisms governing the heat transfer and hydraulic degradation of the heat transport system (HTS). PT diametral creep leads to diametral expansion, which affects the thermal hydraulic characteristics of the coolant channels and the critical heat flux (CHF). The CHF is a major parameter determining the critical channel power (CCP), which is used in the trip setpoint calculations of regional overpower protection (ROP) systems. Therefore, it is essential to predict PT diametral creep in CANDU reactors. PT diametral creep is caused mainly by fast neutron irradiation, temperature and applied stress. The objective of this study was to develop a bundle position-wise linear model (BPLM) to predict PT diametral creep employing previously measured PT diameters and HTS operating conditions. The linear model was optimized using a genetic algorithm and was devised based on a bundle position because it is expected that each bundle position in a PT channel has inherent characteristics. The proposed BPLM for predicting PT diametral creep was confirmed using the operating data of the Wolsung nuclear power plant in Korea. The linear model was able to predict PT diametral creep accurately.
Keywords
Bundle Position-wise Linear Model; Genetic Algorithm; Uncertainty Analysis; Pressure Tube; Diametral Creep Prediction;
Citations & Related Records

Times Cited By Web Of Science : 2  (Related Records In Web of Science)
Times Cited By SCOPUS : 1
연도 인용수 순위
  • Reference
1 D. E. Goldberg, Genetic Algorithms in Search, Optimization, and Machine Learning, Addison Wesley, Reading, Massachusetts (1989).
2 M. Mitchell, An Introduction to Genetic Algorithms, Cambridge, MIT Press, Massachusetts (1996).
3 M. G. Na, "Design of a Genetic Fuzzy Controller for the Nuclear Steam Generator Water Level Control," IEEE Trans. Nucl. Sci., vol. 45, pp. 2261-2271 (1998).   DOI
4 J.W. Hines, B. Rasmussen, "Online sensor calibration monitoring uncertainty estimation," Nuclear Technology, vol. 151, pp. 281-288 (2005).
5 J.W. Hines and R. Seibert, "Technical Review of On-Line Monitoring Techniques for Performance Assessment, Volume 1: State-of-the-Art," NUREG/CR-6895, U.S. Nuclear Regulatory Commission, Washington, D.C. (2006).
6 J.W. Hines, D. Garvey, R. Seibert, and A. Usynin, "Technical Review of On-Line Monitoring Techniques for Performance Assessment, Volume 2: Theoretical Issues," NUREG/CR- 6895, U.S. Nuclear Regulatory Commission, Washington, D.C. (2007).
7 J.W. Hines, J. Garvey, D. Garvey, and R. Seibert, "Technical Review of On-Line Monitoring Techniques for Performance Assessment, Volume 3: Limiting Case Studies," NUREG/CR-6895, U.S. Nuclear Regulatory Commission, Washington, D.C. (2008).
8 R. Tibshirani, "A comparison of some error estimates for neural network models," Neural Computation, vol. 8, pp. 152-163 (1996).   DOI
9 D. Quach, P. Sermer, B. Phan, and O. Nainer, "Improvements in pressure tube diametral creep predictions and statistical error modeling," 28th Annual CNS Conference & 31 SNS/CAN Student Conference, Saint John, New Brunswick, Canada, June 3-6, 2007.
10 1. N. Christodoulou et al., "Modeling In-Reactor Deformation of Zr-2.5Nb Pressure Tubes in CANDU Power Reactors," Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295, E. R. Bradley and G. P. Sabol, Eds., American Society for Testing and Materials, pp. 518-537 (1996).
11 S. L. Chiu, "Fuzzy Model Identification Based on Cluster Estimation," J. Intell. Fuzzy Systems, vol. 2, pp. 267-278 (1994).   DOI   ScienceOn
12 J. H. Holland, Adaptation in Natural and Artificial Systems, Univ. Michigan Press, Ann Arbor, MI (1975).