APPARATUS AND METHOD OF STEAM GENERATOR TUBE PLUGGING ANALYSIS USING PRESSURE DROP AND HEAT-TRANSFER PERFORMANCE

摘要

The present invention relates to plugging and a method for converting the plugging in a state of performing the sleeving of a steam generator of a nuclear reactor and, more specifically, to a device for converting a plugging ratio of the steam generator which considers a pressure drop performance and an electric heat performance. The device (1) for converting the plugging ratio of the steam generator which considers the pressure drop performance and the electric heat performance comprises a sensor unit (10) and a control unit (30). The sensor unit having at least one of temperature sensor, pressure temperature, or flow sensor is installed in an inlet nozzle (180) of the steam generator, the inside of the steam generator, and an outlet nozzle (182) of the steam generator. The control unit determines the plugging ratio after inputting a measured signal of the sensor unit (10) and calculating a plugging ratio converting coefficient with the pressure drop performance and the electric heat performance before and after the sleeving. [Reference numerals] (11,23) Temperature sensor; (13) Pressure sensor; (15) Flow sensor; (200A) Nuclear reactor core; (310) Nuclear reactor hot leg; (340) Nuclear reactor cold leg; (BB) FlowB; (DD) FlowA; (EE,CC) FlowD; (FF) FlowC