Test device for simulating dynamic scaling of secondary side of heat exchange tube of steam generator in pressurized water reactor

Abstract

The invention discloses a test device for simulating dynamic scaling of a secondary side of a heat exchange tube of a steam generator in a pressurized water reactor. The test device comprises a barrel body, a tube bundle assembly, a first barrel head, and a second barrel head. The tube bundle assembly is pushed into the barrel body from a first opening. A sliding assembly is arranged between the tube bundle assembly and the interior of the barrel body, so that the tube bundle assembly can be pushed into or moved out of the barrel body. A first baffle and a second baffle are arranged end to end, so that after the tube bundle assembly is placed into the barrel body, the first baffle seals the first opening, and the second baffle seals a second opening. The barrel body is provided with a second loop inlet and a second loop outlet, and the second loop inlet and the second loop outlet are both communicated with the interior of the barrel body to form a second heat exchange loop. The first barrel head and the second barrel head are detachably connected to the two ends of the barrel body respectively. The first barrel head is provided with a first loop inlet, the second barrel head is provided with a first loop outlet, and the first loop inlet and the first loop outlet are communicated with the two ends of a heat exchange tube respectively to form a first heat exchange loop. The test device is used for researching the scaling process of a heat exchange tube of a steam generator in a pressurized water reactor.

Description

technical field [0001] The invention relates to the technical field of nuclear power, in particular to a test device for simulating dynamic fouling on the secondary side of a heat exchange tube of a pressurized water reactor steam generator. Background technique [0002] The steam generator in the nuclear power plant is the heat exchange equipment of the primary and secondary loops of the nuclear power plant. It mainly transfers the heat in the coolant of the primary loop to the water in the secondary loop to generate steam and drive the steam turbine to generate electricity. The secondary circuit equipment uses more carbon steel and low alloy steel materials, which will form larger Fe3O4 oxides after being oxidized by water, and the formed oxide layer will peel off and enter the water medium of the secondary circuit to become sediment. After evaporation and concentration, these deposits gradually accumulate and adhere to the secondary side of the heat transfer tube, forming...

AI Technical Summary

Problems solved by technology

[0004] During the outage of nuclear power plants, video inspections are usually carried out on areas such as the secondary side tube sheets, and the inspection range of related technologies is limited, and it is impossible to inspect all heat transfer tube bundles and supporting structures

Or use eddy current inspection, but this method can only detect cracks on the surface and inlet surface of metal pipes

Chinese invention application (the title of the invention is a method for evaluating heat exchanger fouling, the publication number is CN111727352A), the device monitors the water level in the steam generator through a pressure sensor, and the corresponding calculation can only indicate the tendency and level of fouling, However, it is impossible to specifically detect and analyze the fouling components on the secondary side of the heat transfer tube

Images