DocumentCode
1299734
Title
Monitoring and Uncertainty Analysis of Feedwater Flow Rate Using Data-Based Modeling Methods
Author
Yang, Heon Young ; Lee, Sung Han ; Na, Man Gyun
Author_Institution
Dept. of Nucl. Eng., Chosun Univ., Gwangju, South Korea
Volume
56
Issue
4
fYear
2009
Firstpage
2426
Lastpage
2433
Abstract
The Venturi flow meters that are being used to measure the feedwater flow rate in most pressurized water reactors are confronted with fouling phenomena, resulting in an overestimation of the flow rate. In this paper, we will therefore develop two soft-sensing models based on a fuzzy inference system and support vector regression for online prediction of the feedwater flow rate. The data-based models are developed using a training data set and a verification data set, and validated using an independent test data set. These data sets are divided from the startup data of Yonggwang Nuclear Power Plant Unit 3. The data for training the data-based models is selected with the aid of a subtractive clustering scheme because informative data increases the learning effect. The uncertainty of the data-based models is analyzed using 100 sampled training and verification data sets, and a fixed test data set. The prediction intervals are very small, which means that the predicted values are very accurate. The root mean square error and relative maximum error of the models were quite small. Also, the residual signal between the measured value and the estimated value is used to determine the overmeasure due to the fouling phenomena by a sequential probability ratio test which consequently monitors the existing feedwater flow meters.
Keywords
fission reactor cooling; fission reactor theory; flowmeters; fuzzy reasoning; learning (artificial intelligence); light water reactors; mean square error methods; nuclear engineering computing; nuclear power stations; probability; regression analysis; support vector machines; Venturi flow meters; Yonggwang nuclear power plant unit 3; data-based modeling methods; emergency core cooling system; feedwater flow rate; fouling phenomena; fuzzy inference system; monitoring algorithms; pressurized water reactors; root mean square error; sequential probability ratio test; soft-sensing models; subtractive clustering scheme; support vector regression; training data set; uncertainty analysis; verification data set; Fluid flow measurement; Fuzzy systems; Inductors; Monitoring; Power generation; Power system modeling; Predictive models; Testing; Training data; Uncertainty; Data-based model; feedwater flow rate; fuzzy inference; genetic algorithm; sequential probability ratio test; subtractive clustering; support vector regression (SVR);
fLanguage
English
Journal_Title
Nuclear Science, IEEE Transactions on
Publisher
ieee
ISSN
0018-9499
Type
jour
DOI
10.1109/TNS.2009.2022366
Filename
5204684
Link To Document