Authors:
Soon Ho Park
;
Jae Hwan Kim
;
Dae Seop Kim
and
Man Gyun Na
Affiliation:
Chosun University, Korea, Republic of
Keyword(s):
Group Method of Data Handling (GMDH), Uncertainty Analysis, LOCA (Loss of Coolant Accidents), Prediction of Break Size.
Related
Ontology
Subjects/Areas/Topics:
Informatics in Control, Automation and Robotics
;
Intelligent Control Systems and Optimization
;
Intelligent Fault Detection and Identification
Abstract:
When transients or accidents occur in the nuclear power plants, the plant operators and technical staffs are provided with only partial information and faced with a number of signals and alarms. Therefore, providing information such as a break size in case of LOCA is essential to control these events successively. In this paper, in order to predict the LOCA break size, a prediction model was developed by using group method of data handling (GMDH) algorithm, and we have conducted its uncertainty analysis. The proposed prediction model was verified using the acquired data from the OPR1000 nuclear power plant.