Nuclear reactor pressure regulator safety valve water seal test system and method

A kind of technology of pressure stabilizer safety valve and nuclear reactor, which is applied in the testing of machine/structural parts, instruments, testing of mechanical parts, etc.

Active Publication Date: 2018-06-19
XI AN JIAOTONG UNIV
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AI Technical Summary

Problems solved by technology

[0004] The purpose of the present invention is to provide a hydraulic water seal that can restore the reactor pressurizer safety valve hydraulic water seal to the greatest extent in view of the fact that the above-mentioned test device or test system is not applicable or does not meet the needs of the nuclear engineering field for the hydraulic water seal test research of the pressurizer safety valve. The

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  • Nuclear reactor pressure regulator safety valve water seal test system and method

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Embodiment Construction

[0034] Below in conjunction with accompanying drawing and embodiment the present invention is described in detail:

[0035] Such as figure 1 As shown, a nuclear reactor pressurizer safety valve water seal test system includes a deionized water production system 1, a first supplementary water pump 201 connected to the first flow control valve 801 of the deionized water production system, and the first supplementary water pump 201 is additionally One end is connected to the heating water tank 3, and the lower end of the heating water tank 3 is connected to the first drain valve 802. At the same time, the heating water tank 3 has multiple sets of heating rods built in, and the power of each heating rod is 60kW; A differential pressure transmitter 1001; the first temperature sensor 901 is installed at the outlet of the heating water tank 3; in the circuit, it serves to provide deionized water lower than the saturation temperature for the test circuit, and at the same time ensures ...

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Abstract

The invention discloses a nuclear reactor pressure regulator safety valve water seal test system and method. A circuit can carry out low-pressure and medium-pressure hydraulic water seal experiments under vacuum, air and multi-component non-condensable gas, and reveals the water seal process and the hydraulic water seal mechanism phenomenon of the hydraulic water seal structure. The circuit mainlyincludes a deionized water system, a heating water tank, a hot water pump, a pressure vessel, a vacuum pump, a non-condensable gas, an exhaust pressure relief port, a water seal experimental section,and a control and acquisition system. The experimental pressure range is from 0.1 to 1.0 MPa and the temperature range is 0 to 180 degrees centigrade. The experimental circuit of the present invention can realize the visualization of the experimental phenomenon of the water seal structure. The circuit pressure vessel is designed in an integrated manner and has multiple sensing devices. The systemand method have the advantages of high safety, high precision of experimental data, and easy installation and maintenance.

Description

technical field [0001] The invention belongs to the technical field of nuclear power equipment performance verification test research, and in particular relates to a nuclear reactor voltage stabilizer safety valve water seal test system and a test method thereof. Background technique [0002] The nuclear power plant voltage stabilizer is an important device for maintaining the pressure of the primary circuit at a set value and regulating the pressure of the primary circuit. A water seal structure is installed upstream of the safety valve of the pressurizer to reduce the leakage of hydrogen in the vapor phase space of the pressurizer to the pressure relief box through the safety valve, and reduce the hydraulic load on the pipeline downstream of the safety valve and the nozzle of the safety valve of the pressurizer And slow down the temperature fluctuation of the safety valve. As early as the end of the 19th century, British turbulence expert Reynolds studied how U-shaped pip...

Claims

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Application Information

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IPC IPC(8): G01M13/00G01M3/28
Inventor 向延巫英伟王明军谭冰田文喜秋穗正苏光辉
Owner XI AN JIAOTONG UNIV
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