JOURNAL BROWSE
Search
Advanced SearchSearch Tips
Fault Detection Sensitivity of a Data-driven Empirical Model for the Nuclear Power Plant Instruments
facebook(new window)  Pirnt(new window) E-mail(new window) Excel Download
 Title & Authors
Fault Detection Sensitivity of a Data-driven Empirical Model for the Nuclear Power Plant Instruments
Hur, Seop; Kim, Jae-Hwan; Kim, Jung-Taek; Oh, In-Sock; Park, Jae-Chang; Kim, Chang-Hwoi;
  PDF(new window)
 Abstract
When an accident occurs in the nuclear power plant, the faulted information might mislead to the high possibility of aggravating the accident. At the Fukushima accident, the operators misunderstood that there was no core exposure despite in the processing of core damage, because the instrument information of the reactor water level was provided to the operators optimistically other than the actual situation. Thus, this misunderstanding actually caused to much confusions on the rapid countermeasure on the accident, and then resulted in multiplying the accident propagation. It is necessary to be equipped with the function that informs operators the status of instrument integrity in real time. If plant operators verify that the instruments are working properly during accident conditions, they are able to make a decision more safely. In this study, we have performed various tests for the fault detection sensitivity of an data-driven empirical model to review the usability of the model in the accident conditions. The test was performed by using simulation data from the compact nuclear simulator that is numerically simulated to PWR type nuclear power plant. As a result of the test, the proposed model has shown good performance for detecting the specified instrument faults during normal plant conditions. Although the instrument fault detection sensitivity during plant accident conditions is lower than that during normal condition, the data-drive empirical model can be detected an instrument fault during early stage of plant accidents.
 Keywords
Data-driven empirical model;NPP instruments;Fault detection;Normal operation;Accident conditions;
 Language
Korean
 Cited by
 References
1.
Heo, G. Y, "Condition Monitoring Using Empirical Models; Technical Review and Prospects for Nuclear Applications," Nuclear Engineering and Technology 40(1) p 49-68, 2008. crossref(new window)

2.
NUREG/CR-5903, "Validation of Smart Sensor Technologies for Instrument Calibration Reduction in Nuclear Power Plants", 1993.

3.
NUREG/CR-6343, "On-Line Testing of Calibration of Process Instrumentation Channels in Nuclear Power Plants", 1995.

4.
EPRI TR-104965, "On-Line Monitoring of Instrument Channel Performance", 2000.

5.
Hines, J. W. et.al.] D. Garvey, R. Seibert, A Usynin, and S.A. Arndt, "Technical Review of On-line Monitoring Techniques for Performance Assesment (NUREG/CR-6895) Vol. 2, Theoretical Issues", May 2008.

6.
Wald, A. "Sequential Tests of Statistical Hypotheses." Annals of Mathematical Statistics 16 (2) 117-186, 1945. crossref(new window)

7.
Jae-Chang Park, "Equipment and Performance Upgrade of Compact Nuclear Simulator", KAERI/RR-1967/1999, KAERI, 1999.