Design of data-driven model for the pressurizer system in nuclear power plants using a TSK fuzzy neural network

被引:4
作者
Mahmoud, Tarek A. [1 ]
Sheta, Amal A. [2 ]
Fikry, Refaat M. [2 ]
Ali, Elsayed H. [2 ]
El-Araby, Sayed M. [2 ]
Mahmoud, Mohammed I. [1 ]
机构
[1] Menoufia Univ, Fac Elect Engn, Dept Ind Elect & Control Engn, Menoufia 32952, Egypt
[2] Nucl Res Ctr, Engn Dept, Egyptian Atom Energy Author, Cairo, Egypt
关键词
Data -Driven Modeling; TSK Fuzzy Neural Network; Pressurizer System; Nuclear Power Plants; WATER-REACTOR; ARTIFICIAL-INTELLIGENCE; REGRESSION; BEHAVIOR; UNIT;
D O I
10.1016/j.nucengdes.2022.112015
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
In pressurized water reactors (PWRs), the main role of the pressurizer unit is to maintain the primary circuit pressure of the reactor within preset limits. To ensure this role, the pressure and the water level control systems for the pressurizer system are very significant. Hence, it is very important to monitor and predict them with great accuracy during operation. In this paper, a data-driven model using a TSK fuzzy neural network (TSKFNN) for the prediction of the pressure and the water level inside the pressurizer is developed. The identification task of the TSKFNN model of the pressurizer system is fulfilled in two steps: the structure and the parameters identification. In the first step, the fuzzy C-means clustering method is used to separate the input data into clusters and obtain the rule antecedent parameters of the TSKFNN model. Besides, the initial values of the rule consequent parameters are defined using the kernel ridge regression algorithm. In the second step, the sliding-window Kernel Recursive Least Squares (KRLS) algorithm and the gradient method are developed to adapt TSKFNN model parameters. By using input/ output data collected from the PCTran VVER-1200 simulator, the data-driven model was trained, tested, and evaluated. The simulation results demonstrate that the data-driven model using the TSKFNN structure can effectively predict the pressure and the water level in the pressurizer system. Furthermore, the simulation results also involve a comparison with two other mathematical models to confirm the effectiveness of the developed data-driven model.
引用
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页数:21
相关论文
共 56 条
[1]  
Asmolov V. G., 2017, Nuclear Energy and Technology, V3, P260, DOI 10.1016/j.nucet.2017.10.003
[2]  
BAEK SM, 1986, NUCL TECHNOL, V74, P260
[3]   Simulating and evaluating the pressurizer dynamic behavior in various sizes [J].
Baghban, Ghonche ;
Shayesteh, Mohsen ;
Bahonar, Majid ;
Sayareh, Reza .
PROGRESS IN NUCLEAR ENERGY, 2016, 93 :406-417
[4]  
Bezdek J. C., 1981, Pattern recognition with fuzzy objective function algorithms
[5]   A study of different cases of VVER reactor core flooding in a large break loss of coolant accident [J].
Bezrukov, Yury Alekseevich ;
Schekoldin, Vladimir Ivanovitc ;
Zaitsev, Sergey Ivanovich ;
Churkin, Andrey Nikolaevich ;
Lisenkov, Evgeny Aleksandrovich .
EPJ NUCLEAR SCIENCES & TECHNOLOGIES, 2016, 2
[6]   A new T-S fuzzy model predictive control for nonlinear processes [J].
Boulkaibet, Ilyes ;
Belarbi, Khaled ;
Bououden, Sofiane ;
Marwala, Tshilidzi ;
Chadli, Mohammed .
EXPERT SYSTEMS WITH APPLICATIONS, 2017, 88 :132-151
[7]   Support vector learning mechanism for fuzzy rule-based modeling: A new approach [J].
Chiang, JH ;
Hao, PY .
IEEE TRANSACTIONS ON FUZZY SYSTEMS, 2004, 12 (01) :1-12
[8]   Application of artificial intelligence techniques in modeling and control of a nuclear power plant pressurizer system [J].
de Oliveira, Mauro Vitor ;
Soares de Almeida, Jose Carlos .
PROGRESS IN NUCLEAR ENERGY, 2013, 63 :71-85
[9]  
Des U., 2018, CONTR COMM PRED NONL
[10]  
Dwiddar M.S., 2014, PHYTRA 3 3 INT C PHY, DOI [10.13140/2.1.4876.1281, DOI 10.13140/2.1.4876.1281]