CN204944775U - Gate valve for nuclear power plant online lumen pressurization test unit - Google Patents

Abstract

An on-line chamber pressurized seal test device for a nuclear power plant gate valve, including a gate valve to be tested, characterized in that it also includes a test medium source, a leak detector and a test pressure tube, and the test medium source passes through the connection between the test pressure tube and the leak detector. One end is connected; the other end of the leak detector is sealed and connected with the packing purge port of the gate valve under test through the test pressure pipe. The beneficial effects of the utility model are: when the sealing performance of the gate valve can be detected online, the detection interference can be eliminated, and a more accurate detection method can be improved; since the cavity volume of the gate valve is small, the detection time is short, and the radiation dose of the detection personnel can be effectively reduced.

Description

Nuclear power plant gate valve online cavity pressurized sealing test device

technical field

The utility model relates to a test device used in nuclear power plants for on-line testing of the sealing performance of gate valves that function as isolation, and is suitable for all gate valves (including W, C and V gate valves) with packing purge holes.

Background technique

With the massive emission of greenhouse gases and the rising global temperature, energy conservation and emission reduction has become a hot issue of sustainable development in the world. Under the background of my country's emphasis on improving energy structure and vigorously developing new energy sources, nuclear power, as a clean energy source, is producing a large amount of electricity for human beings.

In various process systems of nuclear power plants, many large isolation valves are in the form of gate valves.

At present, the online detection of the sealing performance of the gate valve adopts the method of isolating a pressurized area in the system where the valve to be tested is located, and the area is tested by the flow supplement method or the pressure decay method. However, due to the complex isolation of the system, it is impossible to distinguish the leakage of the tested valve and other valves in the pressurized area, resulting in low accuracy of online detection. In addition, the online detection of environmental radiation doses is high, which often requires a large investment of manpower and material resources, and the detection takes a long time. A difficult problem for personnel.

Contents of the invention

In order to accurately detect the sealing performance of the gate valve on-line, the utility model provides an online chamber pressurized sealing test device for the gate valve of a nuclear power plant, which can not only detect the sealing performance of the gate valve on-line, but also eliminate the interference of other valves on the detection results and shorten the detection time .

The technical solution adopted by the utility model to solve the technical problem is: an online cavity pressurized sealing test device for a gate valve of a nuclear power plant, which includes a gate valve to be tested, and is characterized in that it also includes a test medium source, a leak detector and a test pressurized tube , the test medium source is connected to one end of the leak detector through the test pressure tube; the other end of the leak detector is sealed and connected to the packing purge port of the gate valve under test through the test pressure tube.

The test medium source is a gas cylinder; the leak detector adopts the JLY-IV type local leak detector.

The packing purge port of the tested gate valve is connected with the test pressurized pipe through a special connector.

The beneficial effects of the utility model are: when the sealing performance of the gate valve can be detected online, the detection interference can be eliminated, and a more accurate detection method can be improved; since the cavity volume of the gate valve is small, the detection time is short, and the radiation dose of the detection personnel can be effectively reduced.

Description of drawings

Fig. 1 is a schematic diagram of the overall structure of an embodiment of the utility model.

Figure 2 is a cross-sectional view of a typical gate valve structure.

Notes in the figure: 1. Gas cylinder, 2. Pressure reducing valve, 3. Wide range fine-tuning leak detector, 4. Test pressure tube, 5. Tested gate valve, 50. Leakage tube, 51. Valve cover, 52 , Disc, 53, valve seat, 54, packing gland, 55, nut, 56 screw, 57, connector, 58, gasket, 59, packing.

detailed description

Referring to Fig. 1 and Fig. 2, the utility model is an online chamber pressurized sealing test device for a gate valve of a nuclear power plant, which includes a gate valve 5 to be tested, and is characterized in that it also includes a test medium source (gas cylinder 1), LY-IV type local detection The leak meter 3 and the test pressurized pipe 4, the test medium source 1 is connected to one end of the leak detector 3 through the test pressurized pipe 4; The sweep port 60 is sealed and connected with the connector 57 (adding a gasket 58).

When using the utility model to test, the test medium generally adopts gas, and the test medium source is generally a gas cylinder 1 with a pressure reducing valve 2; the inside of the leak detector 1 includes a mass flow meter, a pressure gauge, a thermometer, a display screen and a control memory storage circuit (prior art). The test port of the gate valve 5 to be tested is the original packing purge port (remove the original cock of the packing purge port), screw the connector 57 with the same thread as the cock into the position of the original plug, and connect it with a test One end of the pressure tube 4 is connected. The leak detector 3 measures the mass flow rate of the medium passing through it under the test pressure, and detects the leakage rate of the gate valve 5 under test according to the flow supplement method, so as to evaluate the sealing performance of the gate valve.

The utility model uses a wide-range micro-control leak detector to pressurize the middle cavity of the gate valve, and adopts a flow supplement method so that the pressurized area only involves the gate valve to be tested, thereby eliminating the interference of other valves on the detection and improving the online sealing performance detection of the gate valve. Accuracy.

Claims (3)

1. A nuclear power plant gate valve online chamber pressurized sealing test device, including the gate valve to be tested, is characterized in that it also includes a test medium source, a leak detector and a test pressurized tube, and the test medium source passes through the test pressurized tube and the leak detector One end of the leak detector is connected; the other end of the leak detector is sealed and connected with the packing purge port of the tested gate valve through the test pressure pipe. 2. The on-line chamber pressurized seal test device for nuclear power plant gate valves according to claim 1, characterized in that the test medium source is a gas cylinder; the leak detector adopts a JLY-IV local leak detector. 3. The on-line chamber pressurized sealing test device for nuclear power plant gate valve according to claim 1, characterized in that the packing purge port of the gate valve to be tested is connected to the test pressurized pipe through a special connector.