Test device for simulating entrainment of reactor hot leg section

Abstract

The invention discloses a test device for simulating entrainment of a reactor hot leg section. The test device comprises: a first pipe, wherein the first end of the first pipe is connected with a pressure vessel outlet of a reactor; a second pipe; a three-way pipe, wherein the three-way pipe comprises a first end, a second end and a third end, the first end of the three-way pipe is connected withthe second end of the first pipe, the second end of the three-way pipe is connected with the first end of the second pipe, the third end of the three-way pipe is used for being connected with an automatic pressure relief system of the reactor, and the three-way pipe is made of polycarbonate; and a third pipe, wherein the first end of the third pipe is connected with the second end of the second pipe, the first end of the third pipe is connected with the evaporator inlet of the reactor, and the third pipe is bent. According to the test device for simulating entrainment of the reactor hot leg section, double-end air inflow can be achieved, the test device can be used for carrying out air-water entrainment experiment research at the normal temperature and steam-water entrainment experiment research at the high temperature, test observation is facilitated, and the bent third pipe can simulate the real structure of the reactor hot pipe section.

Description

technical field [0001] The invention belongs to the technical field of nuclear experiment devices, and in particular relates to a test device for simulating entrainment in the hot leg section of a reactor. Background technique [0002] The tee structure is widely used in nuclear power plants. Taking AP1000 of the third-generation nuclear power plant as an example, the heat pipe section and the fourth-stage automatic depressurization system (the forth Automatic Depressurization System, ADS-4) pressure relief pipeline have a three-way pipe structure. ADS is an important part of the AP1000 passive safety system. When a small breach accident occurs, the opening of the ADS-4 burst valve can effectively reduce the pressure of the pressure vessel in the later stage of the accident, and realize the In-Containment Refueling Water Storage Tank (In-ContainmentRefuelingWaterStorage Tank, IRWST) internal cooling water is injected into the core under the action of gravity to prevent the ...

AI Technical Summary

Problems solved by technology

At the same time, after the ADS-4 valve was opened, the core pressure continued to decrease, and with the flashing of a large amount of steam, the coolant charge in the primary circuit continued to decrease, which may lead to serious accidents such as core exposure or even burning. The experimental research of two-phase entrainment is mainly based on single-end intake, but this is not consistent with the actual situation, and cannot accurately simulate the prototype reactor

[0004] In the related technology, the hardness of the tee pipe is high, and it is easy to break when the pipe vibrates, so it can only be used for low flow experiments

And it is impossible to carry out the steam-water entrainment experiment under normal pressure. Therefore, it cannot meet the requirements of the ADS-4 entrainment experiment and the steam-water entrainment experiment under a large flow rate, and it cannot better simulate the real structure of the prototype reactor.

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