데이터 기반 경험적 모델의 원전 계측기 고장검출 민감도 평가

다국어 초록 (Multilingual 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.

목차 (Table of Contents)

• Abstract
• 1. 서론
• 2. 데이터 기반 경험적 모델
• 3. 계측기 고장검출 민감도 평가
• 4. 결론
• References

참고문헌 (Reference)

• 1 Hines, J. W., "Technical Review of On-line Monitoring Techniques for Performance Assesment (NUREG/CR-6895) Vol. 2, Theoretical Issues"
• 2 Wald, A., "Sequential Tests of Statistical Hypotheses" 16 (16): 117-186, 1945
• 3 "NUREG/CR-6343, On-Line Testing of Calibration of Process Instrumentation Channels in Nuclear Power Plants"
• 4 "NUREG/CR-5903, Validation of Smart Sensor Technologies for Instrument Calibration Reduction in Nuclear Power Plants"
• 5 Jae-Chang Park, "Equipment and Performance Upgrade of Compact Nuclear Simulator" KAERI 1999
• 6 "EPRI TR-104965, On-Line Monitoring of Instrument Channel Performance"
• 7 GYUN YOUNG HEO, "CONDITION MONITORING USING EMPIRICAL MODELS: TECHNICAL REVIEW AND PROSPECTS FOR NUCLEAR APPLICATIONS" 한국원자력학회 40 (40): 49-68, 2008