本发明公开了一种核反应堆异型棒束通道两相流测量方法。该手段包括：布置于棒束通道内的子通道空泡仪，作为传感器的10贴片电极，用于提供精确正弦波电流的激励源，用于接收控制指令和发送数据的通信系统，用于将交流电压信号转化成直流电压信号的处理电路。本发明通过Comsol计算对异型棒束通道使用子通道空泡仪的电极布置方式进行了方案优化，然后将采集的电压信号跟空泡份额通过标定的方式得到反应堆异型棒束通道两相流动特性，同时开发了一种特定的标定手段保证标定结果的可靠性，具有原理简单、能够有效探测棒束通道内部两相流分布的特点。

This invention discloses a measurement method for two-phase flow in nuclear reactor metatypical fuel rod bundle channels. The methodology includes the following components: subchannel void fraction meters arranged within the rod bundle channels as sensors, ten patch electrodes serving as a precise sinusoidal current excitation source, a communication system for receiving control commands and transmitting data, and a processing circuit for converting AC voltage signals to DC voltage signals. The present invention optimizes the arrangement of electrodes using subchannel void fraction meters in metatypical fuel rod bundle channels through Comsol simulations, and subsequently obtains the characteristics of two-phase flow in reactor fuel rod bundle channels by correlating the collected voltage signals with void fraction using a calibrated approach. Furthermore, a specific calibration procedure is developed to ensure the reliability of the calibration results. The proposed method exhibits the advantages of simplicity in principle and effective detection of the distribution of two-phase flow within the rod bundle channels.