Reactor noise measurements in the safety and regulating systems of CANDU stations

被引:7
|
作者
Glöckler, O [1 ]
机构
[1] Ontario Power Generat Nucl, Nucl Safety Anal Div, Nucl Anal Dept, Reactor Performance Monitoring Sect, Toronto, ON M5G 1X6, Canada
关键词
reactor noise analysis; in-core flux detectors; flow transmitters; response time; fuel channel vibration; detector tube vibration; detector fault monitoring;
D O I
10.1016/S0149-1970(03)00008-8
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
Reactor noise measurements of safety and regulating system instrumentation are performed in the CANDU nuclear power stations of Ontario Power Generation (OPG) and Bruce Power. Station signals included in the noise measurements are in-core flux detectors (ICFD), ion chambers (I/C), flow transmitters, pressure transmitters, and resistance temperature detectors (RTD). Their frequency dependent noise signatures are regularly measured during steady-state operation, and are used for parameter estimation and anomaly detection. The specific applications include the following areas: Flux noise measurements to detect and characterize (a) anomalies of in-core flux detectors, ion chambers and their electronics, (b) mechanical vibration of fuel channels and in-core detector tubes induced by coolant/moderator flow. Pressure and flow noise measurements to estimate the in-situ response times of flow/pressure transmitters and their sensing lines installed in the reactor's coolant loops. Temperature noise measurements to estimate the in-situ response times of thermal-well or strap-on type RTDs installed in the reactor's coolant and moderator loops. (C) 2003 Elsevier Science Ltd. All rights reserved.
引用
收藏
页码:75 / 82
页数:8
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