Research on improving the reliability of flow measurement of first circuit coolant medium sampling system in nuclear power plant

Abstract

The accuracy of flowmeter of the first circuit coolant sampling system in nuclear power plant affects the measurement of the Boron meter. If the fault treatment cannot be completed in time, the reactor state needs to be withdrawn, which will affect nuclear safety and cause great economic losses. In this paper, a feasible improvement scheme is proposed by analyzing the causes of instrument failure, researching the optimization direction, and adopting measures such as seismic analysis, prototype verification, split design, and interference suppression, which effectively improves the reliability of nuclear sampling flow measurement in nuclear power plants.