CN214067071U - Sampling detection device for high-pressure air of emergency habitability system of nuclear power plant master control room - Google Patents

Sampling detection device for high-pressure air of emergency habitability system of nuclear power plant master control room Download PDF

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Publication number
CN214067071U
CN214067071U CN202022849650.7U CN202022849650U CN214067071U CN 214067071 U CN214067071 U CN 214067071U CN 202022849650 U CN202022849650 U CN 202022849650U CN 214067071 U CN214067071 U CN 214067071U
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sampling
air
power plant
control room
nuclear power
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CN202022849650.7U
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何东雳
侯涛
刘高勇
章超
刘志强
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Sanmen Nuclear Power Co Ltd
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Sanmen Nuclear Power Co Ltd
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Abstract

The utility model belongs to the technical field of compressed air quality monitoring, specifically discloses a sampling detection device of nuclear power plant master control room emergent habitability system high-pressure air, including the relief pressure valve that loops through the trachea and link to each other, sample tee bend, micronic dust filter, drying tube and emanometer, the relief pressure valve has the air inlet, the air inlet passes through the trachea and is connected with the export of compressed air holding vessel, the emanometer is equipped with the gas vent; the sampling tee joint is provided with three ports, wherein two ports are connected with the air pipe, and the other port is opposite to the air. The utility model discloses simple structure, easy dismounting, the simple operation is quick accurate to the detection of radon content, and the security is good.

Description

Sampling detection device for high-pressure air of emergency habitability system of nuclear power plant master control room
Technical Field
The utility model relates to a compressed air quality monitoring technology field, concretely relates to emergent sample detection device that can stay system highly-compressed air of nuclear power plant's main control room.
Background
A nuclear power plant master control room emergency habitability system belongs to a nuclear safety related system, and mainly aims to provide breathable clean air for personnel in a master control room and prevent airborne radioactive substances from entering the master control room under the condition of serious accident. The system can perform safety-related functions such as ventilation, pressurization, cooling, purification and the like without depending on alternating current power supplies inside and outside the plant, actions of operators or active components. The system is provided with a compressed air storage tank for storing high-pressure compressed air of 24Mpa so as to ensure sufficient air supply capacity, monitoring of radon content is required to be regularly executed, radon is one of four main control indexes in the national indoor air quality standard, and regular radon measurement is used for monitoring the quality of the compressed air so as to ensure the air supply quality.
In order to detect the radon content in the compressed air, a sampling detection device needs to be equipped, and a device adopted in the national standard GB/T14582 + 1993 standard measuring method for radon in ambient air is suitable for sampling under normal pressure air and is not suitable for high-pressure air of an emergency habitability system of a main control room of a nuclear power plant, and the sampling and the detection are separated, so that the whole measuring process consumes long time and has low efficiency. The sampling detection devices disclosed in patents CN206945379U and CN206074314U are suitable for sampling compressed air, but relate to multiple detection indexes such as moisture, oil, dust particles, and microorganisms, and the sampling devices and operations are complicated, so that the sampling devices are inconvenient for field use, and the radon detection is not available, and the applicability is not high.
SUMMERY OF THE UTILITY MODEL
In order to solve the problem, the utility model provides an emergent sample detection device that can stay system highly-compressed air of nuclear power plant's main control room, simple structure, the simple operation is quick accurate to the detection of radon content, and the security is good.
In order to achieve the above purpose, the utility model adopts the following specific technical scheme:
a sampling detection device for high-pressure air of an emergency habitability system of a nuclear power plant main control room comprises a pressure reducing valve, a sampling tee joint, a fine dust filter, a drying pipe and a radon measuring instrument which are sequentially connected through an air pipe, wherein the pressure reducing valve is provided with an air inlet which is connected with an outlet of a compressed air storage tank through the air pipe, and the radon measuring instrument is provided with an air outlet; the sampling tee joint is provided with three ports, wherein two ports are connected with the air pipe, and the other port is opposite to the air.
Preferably, the trachea is a PP tube, the diameter is 0.2-0.4 inch, the weight is light, and the transfer and carrying are convenient.
Preferably, the sampling tee joint is made of silica gel and is conveniently and tightly connected with the PP pipe in a sleeved mode.
Preferably, the indicating type drying agent is filled in the drying tube. The indicating type drying agent is a drying agent which absorbs moisture and changes color, such as copper sulfate, silica gel and the like, and can judge whether the air is completely dried or not according to the color change amount.
Furthermore, the drying tube comprises a shell and a detachable embedded column, and the indicating type drying agent is arranged in the embedded column, so that the structure is convenient for maintenance and replacement of the drying agent.
Preferably, the radon detector is an RAD7 type electronic continuous radon detector, is a portable detector, and has high detection sensitivity, high precision and quick response.
Preferably, the pressure reducing valve is provided with a pressure gauge and a flow gauge.
Preferably, at least two layers of fiber membranes are arranged in the fine dust filter, so that the filtering effect of air is improved, and the service life of the fine dust filter is prolonged.
Furthermore, the pore diameter of the fiber membrane is 200-600nm, and along the direction from the inlet to the outlet of the fine dust filter, the pore diameter of the fiber membrane is sequentially reduced, so that large-particle impurities and small-particle impurities are sequentially removed, and the blockage of the fiber membrane is prevented.
Preferably, a fastener is bound and sealed at the interface of the air pipe and the inlet end of the sampling tee joint. The pressure of the compressed air is still higher than the normal pressure after the pressure of the compressed air is reduced by the pressure reducing valve, and the pressure applied to the interface of the air pipe and the inlet end of the sampling tee joint is high, so that the tightness is ensured by arranging a fastener; the fastener can be a disposable bandage, an adhesive tape, an elastic rope, a rubber band and the like.
The utility model discloses following beneficial effect has:
1. the utility model discloses with relief pressure valve, sample tee bend, micronic dust filter, drying tube and radon meter through the tracheal connection can realize the measurement of radon content in the highly-compressed air, sampling device is simple easily obtained, method easy operation measures high efficiency, and it is all very convenient to install dismouting and part replacement moreover, and the flexibility ratio is high, and the practicality is good.
2. The utility model is used for reducing pressure and adjusting gas flow, the sampling tee joint is used for ensuring that the gas pressure is normal pressure, the dust filter is used for filtering fine particles in air, and the drying pipe is used for dehumidification; the pressure reducing valve and the sampling tee joint are used together to ensure the safety of the operation process, and the use of the micro dust filter and the drying tube improves the purity of air, thereby improving the accuracy of measurement.
3. The utility model is suitable for a nuclear power plant's main control room is emergent can stay the sample detection of radon in the system compressed air, also can use in other compressed air occasions simultaneously.
Drawings
FIG. 1: the structure of the utility model is schematically shown.
In the figure: 1-pressure reducing valve, 2-sampling tee joint, 3-dust filter, 4-drying tube and 5-radon detector.
Detailed Description
The invention is further described with reference to the following figures and specific embodiments.
Examples
A nuclear power plant master control room emergency inhabitable system high-pressure air sampling detection device is shown in figure 1 and comprises a pressure reducing valve 1, a sampling tee joint 2, a fine dust filter 3, a drying pipe 4 and a radon measuring instrument 5 which are sequentially connected through an air pipe, wherein the pressure reducing valve is provided with an air inlet which is connected with an outlet of a compressed air storage tank through the air pipe, and the radon measuring instrument is provided with an air outlet; the sampling tee 2 has three ports, two of which are connected with the air pipe, and the other is empty.
In this embodiment, the air tube is a PP tube, with a diameter of 0.25 inch; the pressure reducing valve 1 is provided with a pressure gauge and a flow meter; the sampling tee joint 2 is made of silica gel, and a plurality of disposable binding belts are bound and sealed at the interface of the air pipe and the inlet end of the sampling tee joint 2; the dust filter 3 comprises a plastic shell, two ends of the plastic shell extend outwards and are sleeved with an air pipe, two layers of fiber membranes are arranged in the plastic shell, the pore diameter of the fiber membrane arranged at the near inlet end of the dust filter 3 is 600nm, and the pore diameter of the fiber membrane arranged at the near outlet end is 200 nm; the drying tube 4 is a Drierite 26800 drying column, and an indicating type drying agent Drierite 23025 anhydrous calcium sulfate is filled in the drying column; the radon measuring instrument 5 is an RAD7 type electronic continuous radon measuring instrument.
The installation of above-mentioned device and the sampling test process to emergent habitability system high-pressure air of nuclear power plant's master control room are as follows:
the method comprises the following steps: the outlet of the compressed air storage tank is connected with a pressure reducing valve 1 through an air pipe;
step two: the rear end of the pressure reducing valve 1 is connected with a sampling tee joint 2 through an air pipe, and the pressure reducing valve 1 is adjusted to enable air flow at the opposite end of the sampling tee joint 2 to be blown out slowly;
step three: sequentially connecting a micro dust filter 3 and a drying tube 4 at the rear end of a sampling tee joint 2 through an air tube, and confirming that the color change amount of the calcium sulfate drying agent in the drying tube 4 is less than 3/4 (the blue color is changed into pink);
step four: the rear end of the drying tube 4 is connected with the inlet end of a radon measuring instrument 5 through an air tube;
step five: sequentially starting a printer and a host power supply of the radon detector 5, and waiting for the self-inspection of the detector to be completed;
step six: setting an instrument to start purification, closing the purification after 10 minutes, and starting automatic measurement by a radon detector 5;
step seven: after the measurement is finished, the gas is discharged from the exhaust port of the emanometer 5, and the test data can be printed; and then the host is closed, the compressed air and the pressure reducing valve 1 are closed, the sampling device is disconnected, and the sampling detection is finished.
This detailed description is to be construed as illustrative only and not limiting, and any changes that may be made by a person skilled in the art after reading the present disclosure are intended to be protected by the patent laws within the scope of the appended claims.

Claims (10)

1. Emergent system high-pressure air's that can live sampling test device, its characterized in that of can staying in nuclear power plant's master control room: the device comprises a pressure reducing valve (1), a sampling tee joint (2), a micro dust filter (3), a drying pipe (4) and a radon measuring instrument (5) which are sequentially connected through an air pipe, wherein the pressure reducing valve is provided with an air inlet which is connected with an outlet of a compressed air storage tank through the air pipe, and the radon measuring instrument is provided with an air outlet; the sampling tee joint (2) is provided with three ports, wherein two ports are connected with an air pipe, and the other port is opposite to the air pipe.
2. The device for sampling and detecting the high-pressure air of the emergency habitability system of the nuclear power plant main control room according to claim 1, wherein: the air pipe is a PP pipe, and the diameter of the air pipe is 0.2-0.4 inch.
3. The device for sampling and detecting the high-pressure air of the emergency habitability system of the nuclear power plant main control room according to claim 1 or 2, wherein: the sampling tee joint (2) is made of silica gel.
4. The device for sampling and detecting the high-pressure air of the emergency habitability system of the nuclear power plant main control room according to claim 1, wherein: and an indicating type drying agent is arranged in the drying pipe (4).
5. The device for sampling and detecting the high-pressure air of the emergency habitability system of the nuclear power plant main control room according to claim 4, wherein: the drying tube (4) comprises a housing and a removable embedded cylinder, wherein the indicating type drying agent is arranged in the embedded cylinder.
6. The device for sampling and detecting the high-pressure air of the emergency habitability system of the nuclear power plant main control room according to claim 1, wherein: the radon measuring instrument (5) is an RAD7 type electronic continuous radon measuring instrument.
7. The device for sampling and detecting the high-pressure air of the emergency habitability system of the nuclear power plant main control room according to claim 1, wherein: the pressure reducing valve (1) is provided with a pressure gauge and a flow meter.
8. The device for sampling and detecting the high-pressure air of the emergency habitability system of the nuclear power plant main control room according to claim 1, wherein: at least two layers of fiber membranes are arranged in the micro dust filter (3).
9. The device for sampling and detecting the high-pressure air of the emergency habitability system of the nuclear power plant main control room according to claim 8, wherein: the pore diameter of the fiber membrane is 200-600nm, and the pore diameters of the fiber membrane are sequentially reduced along the direction from the inlet to the outlet of the fine dust filter (3).
10. The device for sampling and detecting the high-pressure air of the emergency habitability system of the nuclear power plant main control room according to claim 1, wherein: and a fastener is bound and sealed at the interface of the air pipe and the inlet end of the sampling tee joint (2).
CN202022849650.7U 2020-12-02 2020-12-02 Sampling detection device for high-pressure air of emergency habitability system of nuclear power plant master control room Active CN214067071U (en)

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114323824A (en) * 2021-11-25 2022-04-12 中国核电工程有限公司 Tracer gas sampling device and method for habitability area of nuclear power station

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114323824A (en) * 2021-11-25 2022-04-12 中国核电工程有限公司 Tracer gas sampling device and method for habitability area of nuclear power station

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