Prediction of DNBR Using Fuzzy Support Vector Regression and Uncertainty Analysis

被引:20
作者
Lee, Sim Won [1 ]
Kim, Dong Su [1 ]
Na, Man Gyun [1 ]
机构
[1] Chosun Univ, Dept Nucl Engn, Kwangju 501759, South Korea
关键词
Departure from nucleate boiling ratio (DNBR); fuzzy support vector regression (FSVR); self-powered neutron detector (SPND); subtractive clustering; CORE PROTECTION; METHODOLOGY; NETWORK;
D O I
10.1109/TNS.2010.2047265
中图分类号
TM [电工技术]; TN [电子技术、通信技术];
学科分类号
0808 ; 0809 ;
摘要
It is very important for operators to be informed of the departure from nucleate boiling ratio (DNBR) to prevent the fuel cladding from melting and causing a boiling crisis. Artificial intelligence methods such as neural networks and support vector regression (SVR) have extensively and successfully been applied to nonlinear function approximation. In this paper, fuzzy support vector regression (FSVR) combined with a fuzzy concept and SVR is presented to precisely predict the minimum DNBR by using the measured signals of a reactor coolant system, such as reactor power, reactor pressure, and control rod positions. Also, the prediction uncertainty for the predicted minimum DNBR is assessed. It is demonstrated that FSVR is accurate enough to be used in protection and monitoring algorithms for departure from nucleate boiling (DNB). Therefore, FSVR can be used to effectively monitor and predict the minimum DNBR in the reactor core.
引用
收藏
页码:1595 / 1601
页数:7
相关论文
共 21 条
[1]  
*ABB COMB ENG INC, 1986, OV DESCR COR OP LIM
[2]   ESTIMATION OF THE POWER PEAKING FACTOR IN A NUCLEAR REACTOR USING SUPPORT VECTOR MACHINES AND UNCERTAINTY ANALYSIS [J].
Bae, In Ho ;
Na, Man Gyun ;
Lee, Yoon Joon ;
Park, Goon Cherl .
NUCLEAR ENGINEERING AND TECHNOLOGY, 2009, 41 (09) :1181-1190
[3]  
Chiu S., 1994, J INTELL FUZZY SYST, V2
[4]  
CHO BO, 2002, P INT C NEW FRONT NU
[5]   Validation of on-line monitoring techniques to nuclear plant data [J].
Garvey, Jamie ;
Garvey, Dustin ;
Seibert, Rebecca ;
Hines, J. Wesley .
NUCLEAR ENGINEERING AND TECHNOLOGY, 2007, 39 (02) :133-142
[6]   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) [J].
Han, S ;
Kim, US ;
Seong, PH .
ANNALS OF NUCLEAR ENERGY, 1999, 26 (06) :471-488
[7]   Condition monitoring using empirical models: Technical review and prospects for nuclear applications [J].
Heo, Gyun Young .
NUCLEAR ENGINEERING AND TECHNOLOGY, 2008, 40 (01) :49-68
[8]   Online sensor calibration monitoring uncertainty estimation [J].
Hines, JW ;
Rasmussen, B .
NUCLEAR TECHNOLOGY, 2005, 151 (03) :281-288
[9]   Assessment of core protection and monitoring systems for an advanced reactor SMART [J].
In, WK ;
Hwang, DH ;
Yoo, YJ ;
Zee, SQ .
ANNALS OF NUCLEAR ENERGY, 2002, 29 (05) :609-621
[10]   Development of a back propagation network for one-step transient DNBR calculations [J].
Kim, HC ;
Chang, SH .
ANNALS OF NUCLEAR ENERGY, 1997, 24 (17) :1437-1446