CRDM/RPI test device for nuclear power plant reactor control system

Abstract

The invention, which is suitable for the nuclear power safety technology, provides a CRDM / RPI test device for a nuclear power plant reactor control system. The device comprises a multi-core-diameter input test port for being plugged with a cabinet probe of the reactor control system to obtain measurement data, a resistance test switch and an insulation test switch, wherein the switches are used for testing path switching. A plurality of switching terminals of the resistance test switch and the insulation test switch are connected with a plurality of core diameters of the multi-core-diameter input test port by wires; and selective output terminals of the resistance test switch and the insulation test switch are connected with measuring units externally or are provided with built-in measuring units for continuity and insulation measurement. The multi-core-diameter input test port is connected with a joint in the cabinet directly and switching between a plurality of measuring groups is completed by rotating the resistance test switch or the insulation test switch; high-efficiency continuity testing can be carried out on the reactor control system by one person, so that the manpower spent in repeated plugging can be avoided and the work efficiency can be improved; and the working time of main line repairing can be reduced.

Description

technical field [0001] The invention belongs to the technical field of nuclear power safety, and in particular relates to a CRDM / RPI testing device for a reactor control system of a nuclear power plant. Background technique [0002] In the nuclear power system, the reactor control system (RGL) is one of the important control systems in the nuclear power plant, and it needs to be tested and repaired regularly. At present, the CRDM / RPI test box is usually used as the special test tool for the reactor control system (RGL). During the overhaul, it is used to test the insulation and continuity of the control rod drive coil (CRDM) and the rod position measurement coil (RPI), so as to eliminate the possible defects of the control rod drive coil (CRDM) and the rod position measurement coil (RPI). Thus ensuring the safe and stable operation of the unit in the next cycle. [0003] There are four control rod drive coils (CRDM) in the reactor control system (RGL) cabinet, which are res...

AI Technical Summary

Problems solved by technology

[0004] The purpose of the embodiments of the present invention is to provide a CRDM / RPI test device for the reactor control system of a nuclear power plant, aiming at solving the problem that the upgraded reactor control system (RGL) cannot be efficiently and continuously tested at present

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