热管段液位静态特性分析及工程测量监督优化

Static Characterization Analyse of Liquid Level in Hot Pipe Segment and Optimization of Engineering Measurement Supervision

在核安全电气设备的监督检查过程中,对安全级分布式控制系统的反应堆保护和监测功能进行独立验证时,发现在核电机组正常运行情况下,热管段中测量液位的核级差压式液位计存在持续向安全显示单元发出超量程质量码报警信号的问题。从法规合规性、仪表精度和测量系统整体可用性的角度,通过密闭式差压液位计测量分析、通道不确定度计算,分析了热管段液位在正常运行和停堆工况下的静态特性及精度符合性。根据设备特点提出了满足工程应用需求的纠正措施,以及应对仪表超量程问题的解决方案。

During the supervision and inspection of nuclear safety electrical equipment,independent verification of the reactor protection and monitoring functions of the safety-grade distributed control system revealed that the nuclear-grade differential-pressure level gauge measuring liquid level in the hot pipe segment has the problem of continuously sending out an over-range quality code alarm signal to the safety display unit under normal operation of the nuclear power unit.From the perspectives of regulatory compliance,instrument accuracy and overall usability of the measurement system,the static characteristics and accuracy compliance of the liquid level in the hot pipe segment under normal operation and reactor shutdown conditions are analyzed through the measurement analysis of the closed differential pressure liquid level gauge and the calculation of channel uncertainty.Corrective measures to meet the requirements of engineering applications and solutions to cope with the over-range problem of the meter are proposed according to the characteristics of the equipment.