Vibration Monitoring System for Elements of the Primary Coolant Circuit of Power Generating Units at Nuclear Power Stations Equipped with VVER-440 Reactors

摘要

The results obtained from investigations into vibration monitoring of elements operating in the primary coolant circuit of the VVER-440 reactor power unit at the Armenian nuclear power station are considered, and the process of quantitatively estimating the monitored parameters (vibration acceleration, velocity, and displacement) is described. The form of presenting output data with appropriate messages regarding the vibration state of elements is determined.