目前,在核反应堆系统中,往往采用工艺管道的直角弯头两侧产生的压差进行流体的流量测量。也有采用节流式流量计测量冷却剂流量,但是由于工艺管道紧凑,不可能满足节流式流量计的安装技术条件。所以一般来说,必须建立一个大型的模拟装置,对流量计进行实际标定,这是一项十分繁杂的工作。另外随着核反应堆冷却剂 Currently, in nuclear reactor systems, fluid pressure is often measured by the pressure differential across the right-angle elbow of the process piping. There are also throttled flowmeters that measure coolant flow, but due to the tightness of the process piping, it is not possible to meet the throttling flowmeter installation specifications. So in general, you have to build a large analog device, the actual calibration of the flow meter, this is a very complicated task. In addition with the nuclear reactor coolant