CN216311363U - Radioactive waste gas treatment device - Google Patents

Radioactive waste gas treatment device Download PDF

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Publication number
CN216311363U
CN216311363U CN202122280012.2U CN202122280012U CN216311363U CN 216311363 U CN216311363 U CN 216311363U CN 202122280012 U CN202122280012 U CN 202122280012U CN 216311363 U CN216311363 U CN 216311363U
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China
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radioactive
waste gas
treatment device
buffer tank
radioactive waste
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CN202122280012.2U
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乔宝权
刘春雨
李晴
林鹏
郑伟
汪栋
王朝晖
周东升
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China General Nuclear Power Corp
China Nuclear Power Technology Research Institute Co Ltd
CGN Power Co Ltd
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China General Nuclear Power Corp
China Nuclear Power Technology Research Institute Co Ltd
CGN Power Co Ltd
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Abstract

The utility model discloses a radioactive waste gas treatment device, which comprises: the device comprises a buffer tank, a compressor, a cooler, a gas-water separator, a protective bed and a delay device which are sequentially connected through pipelines, wherein the buffer tank is connected with a radioactive waste gas source, the delay device is connected with a ventilation system, and a back pressure valve is arranged on the pipeline between the delay device and the ventilation system. Compared with the prior art, the radioactive waste gas treatment device is additionally provided with the compressor between the buffer tank and the cooler, the compressor can compress the radioactive waste gas from the buffer tank and provide stable flow and a pressurization environment for the delay device in cooperation with the pressure reducing valve and the back pressure valve respectively, so that the dynamic adsorption coefficient of the adsorbent in the delay device to the radioactive waste gas is obviously improved under the pressurization operation working condition, and the treatment capacity and the treatment efficiency of the delay device can be improved.

Description

Radioactive waste gas treatment device
Technical Field
The utility model belongs to the technical field of nuclear power, and particularly relates to a radioactive waste gas treatment device.
Background
During reactor operation, nuclear fuel fission generates radionuclides, such as Kr, Xe, and the like. When the fuel cladding is damaged, the radionuclide enters the reactor coolant and is released into the gaseous space to form radioactive hydrogen-containing waste gas. In addition, radioactive waste gases also contain activated elements (e.g., radioactivity I). The radioactivity level of the part of gas is high, and in order to ensure the environmental safety, the part of gas can be discharged only after being treated to reach the standard.
For radioactive waste gas containing inert gas, the compressed storage decay and retention bed adsorption treatment technology is mainly adopted in the industry at present. The compression storage decay technology is that radioactive waste gas is compressed (0.7MPa.g) to decay in a decay tank for 45-60 days, and the radioactive level of the waste gas is monitored and discharged after reaching the standard. However, the compression storage decay technology equipment is huge and occupies a large space. In addition, the pressurized radioactive hydrogen-containing waste gas is stored for a long time under high pressure, so the hydrogen explosion risk is higher and the safety is poorer. Therefore, the method is not suitable for occasions with compact sea piles and high safety requirements.
The detention bed adsorption treatment technology utilizes a porous adsorption medium to adsorb radioactive inert gas, and compared with nitrogen and hydrogen, the inert gas is detained and decayed. The retention bed adsorption treatment technology adopts low-pressure operation, and can realize continuous treatment of radioactive waste gas. However, the retention bed adsorption treatment technology has low treatment capacity, large incoming gas flow and pressure fluctuation, and radioactive particles generated by abrasion of the activated carbon easily flow out along with the gas flow.
SUMMERY OF THE UTILITY MODEL
The utility model aims to: at least one of the shortcomings of the prior art is overcome and a high efficiency radioactive waste gas treatment device is provided.
In order to achieve the above object, the present invention provides a radioactive exhaust gas treatment device, including: the pipeline system comprises a buffer tank, a compressor, a cooler, a gas-water separator, a protective bed and a delay device which are sequentially connected through pipelines, wherein the buffer tank is connected with a radioactive waste gas source, the delay device is connected with a ventilation system, and a back pressure valve is arranged on the pipeline between the delay device and the ventilation system.
According to one embodiment of the radioactive waste gas treatment device, an oxygen concentration monitoring device is arranged on a pipeline between the radioactive waste gas source and the buffer tank.
According to one embodiment of the radioactive waste gas treatment device, the buffer tank is provided with a pressure instrument with a remote transmission function, and pressure data monitored by the pressure instrument is used for controlling the starting and the stopping of the compressor.
According to one embodiment of the radioactive waste gas treatment device, a pressure reducing valve is arranged on a pipeline between the buffer tank and the compressor.
According to one embodiment of the radioactive waste gas treatment apparatus of the present invention, the guard bed is a vertical vessel and is filled with activated carbon or silica gel.
According to one embodiment of the radioactive exhaust gas treatment device according to the present invention, an exhaust filter is provided on a pipe between the delay means and the ventilation system, and the back pressure valve is provided between the exhaust filter and the ventilation system.
According to one embodiment of the radioactive waste gas treatment device, a radioactive monitor and an isolation valve are arranged on a pipeline between the ventilation system and the back pressure valve, and the radioactive monitor interlocks the isolation valve and the compressor.
According to one embodiment of the radioactive exhaust gas treatment device of the present invention, the exhaust filter is a vertical cylinder and is filled with glass fibers.
According to one embodiment of the radioactive waste gas treatment device, a nitrogen purge line is connected to each of a pipeline between the radioactive waste gas source and the buffer tank and a pipeline between the gas-water separator and the protective bed.
According to one embodiment of the radioactive waste gas treatment device, the delay device comprises at least two column containers which are connected in series or in parallel through a pipeline and a valve and are arranged redundantly.
Compared with the prior art, the radioactive waste gas treatment device is additionally provided with the compressor between the buffer tank and the cooler, the compressor can compress the radioactive waste gas from the buffer tank and provide stable flow and a pressurization environment for the delay device in cooperation with the pressure reducing valve and the back pressure valve respectively, so that the dynamic adsorption coefficient of the adsorbent in the delay device to the radioactive waste gas is obviously improved under the pressurization operation working condition, and the treatment capacity and the treatment efficiency of the delay device can be improved.
Drawings
The radioactive waste gas treatment device and the technical effects thereof of the present invention will be described in detail with reference to the accompanying drawings and the detailed description, wherein:
fig. 1 is a schematic structural view of a radioactive waste gas treatment device according to the present invention.
In the figure:
1- -buffer tank; 2- -compressor; 3- -gas cooler; 4- -gas-water separator; 5- -protective bed; 6 to 9-delay means; 10- -discharge filter; 11- -radioactivity monitor; 12- -oxygen concentration monitoring device; 101-pressure reducing valve; 102. 103, 105, 106, 108, 109-stop valve; 104. 107, 110-check valves; 111- -back pressure valve; 112- -an isolation valve; MP-pressure gauge; 20- -source of radioactive exhaust gas; 30- -nitrogen purge line; 40- -Ventilation System.
Detailed Description
In order to make the objects, technical solutions and technical effects of the present invention clearer, the present invention will be described in further detail below with reference to the accompanying drawings and specific embodiments. It should be understood that the detailed description and specific examples, while indicating the preferred embodiment of the utility model, are intended for purposes of illustration only and are not intended to limit the scope of the utility model.
Referring to fig. 1, the present invention provides a radioactive waste gas treatment device, which includes: the device comprises a buffer tank 1, a compressor 2, a cooler 3, a gas-water separator 4, a protective bed 5 and a delay device 6-9 which are sequentially connected through pipelines, wherein the buffer tank 1 is connected with a radioactive waste gas source 20, the delay device 6-9 is connected with a ventilation system 40, and a back pressure valve 111 is arranged on the pipeline between the delay device 6-9 and the ventilation system 40.
The radioactive waste gas treatment device is additionally provided with the compressor 2 between the buffer tank 1 and the cooler 3, the compressor 2 can compress the radioactive waste gas from the buffer tank 1 and provide stable flow and a pressurization environment for the delay devices 6-9 in cooperation with the pressure reducing valve 101 and the backpressure valve 111 respectively, so that the dynamic adsorption coefficient of the adsorbent in the delay devices 6-9 to the radioactive waste gas is obviously improved under the pressurization operation condition, and the treatment capacity and the treatment efficiency of the delay devices 6-9 can be improved.
An oxygen concentration monitoring device 12 is arranged on a pipeline between the radioactive waste gas source 20 and the buffer tank 1, and when the oxygen concentration in the radioactive waste gas exceeds the standard, the oxygen concentration monitoring device 12 isolates upstream incoming gas and gives an alarm. The buffer tank 1 is provided with a pressure instrument with a remote transmission function, and pressure data monitored by the pressure instrument is used for controlling the start and stop of the compressor 2. When the pressure in the buffer tank 1 reaches the preset starting pressure of the compressor 2, the compressor 2 is started in an interlocking manner; when the pressure in the surge tank 1 is lower than the preset shutdown pressure of the compressor 2, the compressor 2 is shut down interlockingly.
And a pressure reducing valve 101 is arranged on a pipeline between the buffer tank 1 and the compressor 2 and used for controlling the pressure of gas entering the compressor 2 to be lower than a limit value range, maintaining the flow rate and pressure of gas delivered by the compressor 2 to be stable and ensuring that the required operation pressure and flow rate of the delay device 6-9 are within the processing capacity range of the delay device 6-9. According to one embodiment of the present invention, the operating pressure can be stably maintained at 0.3 Mpa.
The gas cooler 3 is used to cool the radioactive exhaust gas compressed by the compressor 2 to a temperature within a proper range. The gas-water separator 4 is used for removing moisture in the cooled radioactive waste gas so as to prevent water in the radioactive waste gas from influencing the normal operation of the protective bed 5 and the delay devices 6-9. The guard bed 5 is a vertical vessel and is filled with activated carbon or silica gel.
The delay device comprises at least two column containers (four column containers are included in the illustrated embodiment), the delay device is connected in series or in parallel through pipelines and valves and provided with redundancy, and the operation of three single delay devices is realized through stop valves 102, 103, 105, 106, 108 and 109 and check valves 104, 107 and 110, and one single delay device is in a redundant standby state. The adsorbent replacement ports of the guard bed 5, the delay devices 6 to 9 and the exhaust filter 10 are all provided at the top and can be replaced by an adsorbent replacement device.
The piping between the delay devices 6-9 and the ventilating system 40 is provided with an exhaust filter 10, and a back pressure valve 111 is provided between the exhaust filter 10 and the ventilating system 40 for controlling the pressure inside the device to be stable. The discharge filter 10 is a vertical pressure-bearing filter, is cylindrical and is filled with glass fibers, and the filtering precision of the discharge filter 10 is more than 0.3 mu m.
And a radioactivity monitor 11 and an isolation valve 112 are arranged on a pipeline between the ventilation system 40 and the back pressure valve 111, the radioactivity monitor 11 is used for monitoring radioactivity level parameters of gas at the outlet of the delay device 6-9, and when the radioactivity exceeds the standard, the compressor 2 is controlled to stop running in a linkage mode, and the isolation valve 112 is closed.
A nitrogen purge line 30 is connected to a line between the radioactive waste gas source 20 and the buffer tank 1 for purging the buffer tank 1, the compressor 2, the gas cooler 3, and the gas-water separator 4. The pipeline between the gas-water separator 4 and the guard bed 5 is also connected with a nitrogen purging pipeline 30 for purging the guard bed 5 and the delay devices 6-9 (the system is purged after the oxygen concentration of the system exceeds the standard or the single batch of waste gas treatment is finished).
The operation of the radioactive waste gas treatment device of the present invention is described in detail below with reference to fig. 1:
the radioactive waste gas discharged from the upstream firstly flows into the oxygen concentration monitoring device 12, if the oxygen concentration is not over standard, the radioactive waste gas enters the buffer tank 1, and the buffer tank 1 buffers the fluctuating gas flow and pressure and separates part of moisture in the incoming gas.
When the pressure of the buffer tank 1 is gradually increased to a preset starting pressure value, the compressor 2 is started in an interlocking mode. A pressure reducing valve 101 downstream of the buffer tank 1 reduces the outlet pressure of the buffer tank 1 to a steady value (e.g. 0.025Mpa), and the compressor 2 pressurises the exhaust gas to 0.35Mpa and maintains the delivered exhaust gas flow below 2Nm 3/h.
The air output from the compressor 2 flows into the cooler 3 and the air-water separator 4 in sequence to cool and dehumidify the radioactive waste gas. The cooled and dehumidified radioactive waste gas with stable flow and stable pressure enters the protective bed 5 to further dehumidify the waste gas, and the safe operation of the delay device 6-9 is ensured.
When the first delay device 6 fails, the redundant delay devices are isolated and supplemented, and the specific mode is as follows:
(1) and (4) normal operation: the shut-off valves 102, 106, 108 are opened and the shut-off valves 103, 105, 109 are closed.
(2) Delay device 6 fails: the shut-off valves 103, 105, 108 are opened and the shut-off valves 102, 106, 109 are closed.
The gas at the outlet of the delay device 6-9 enters an exhaust filter 10 to filter and retain the active carbon particles entrained in the gas. The back pressure valve 111 regulates the pressure to 0.3MPa and does not vent when the system pressure is below 0.3 MPa.
After single batch radioactive waste gas treatment, the nitrogen purging function is started, the device is purged, the radioactive hydrogen-containing waste gas in the device is replaced, the radioactive dose in a room can be effectively reduced, the hydrogen concentration in the device is reduced, and the hydrogen explosion risk is reduced.
As can be seen from the above detailed description of the embodiments of the present invention, the radioactive waste gas treatment apparatus of the present invention has the following advantages over the prior art:
the compressor 2 is additionally arranged between the buffer tank 1 and the cooler 3, the compressor 2 can compress the radioactive waste gas from the buffer tank 1, and the compressor 2 is cooperated with the back pressure valve 111 to provide a pressurization environment for the delay devices 6-9 to perform adsorption delayed decay on the radioactive Kr, Xe, I and the like, so that the dynamic adsorption coefficient of the adsorbent in the delay devices 6-9 to the radioactive waste gas under the pressurization operation working condition is obviously improved, and the treatment capacity and the treatment efficiency of the delay devices can be improved.
Through nitrogen purging pipeline 30, oxygen concentration monitoring devices 12 and radioactivity monitoring instrument, carry out real-time supervision, chain control and operation to processing apparatus and purge, consequently can guarantee to discharge up to standard, reduce the hydrogen explosion risk, realize safe operation.
The whole processing device greatly reduces the occupied space, improves the operation adaptability and the safety, is not only suitable for processing the radioactive gas of the offshore floating nuclear power station, but also can be applied to processing the radioactive waste gas in nuclear submarines, nuclear power aircraft carriers, land power stations and other nuclear facilities, and has ideal popularization and application prospects.
The present invention can be modified and adapted appropriately from the above-described embodiments, according to the principles described above. Therefore, the present invention is not limited to the specific embodiments disclosed and described above, and some modifications and variations of the present invention should fall within the scope of the claims of the present invention. Furthermore, although specific terms are employed herein, they are used in a generic and descriptive sense only and not for purposes of limitation.

Claims (10)

1. A radioactive exhaust treatment device, comprising: the pipeline system comprises a buffer tank, a compressor, a cooler, a gas-water separator, a protective bed and a delay device which are sequentially connected through pipelines, wherein the buffer tank is connected with a radioactive waste gas source, the delay device is connected with a ventilation system, and a back pressure valve is arranged on the pipeline between the delay device and the ventilation system.
2. The radioactive exhaust gas treatment device according to claim 1, wherein an oxygen concentration monitoring device is provided on a pipe between the radioactive exhaust gas source and the buffer tank.
3. The radioactive waste gas treatment device according to claim 1, wherein a pressure gauge having a remote transmission function is provided on the buffer tank, and pressure data monitored by the pressure gauge is used for controlling the start and stop of the compressor.
4. The radioactive exhaust treatment device according to claim 1, wherein a pressure reducing valve is provided in a line between the buffer tank and the compressor.
5. The radioactive exhaust treatment device according to claim 1, wherein the guard bed is a vertical vessel and is filled with activated carbon or silica gel.
6. The radioactive exhaust treatment device according to claim 1, wherein an exhaust filter is provided on the pipe between the delay means and the ventilation system, and the back pressure valve is provided between the exhaust filter and the ventilation system.
7. The radioactive exhaust gas treatment device according to claim 6, wherein a radioactivity monitor and an isolation valve are arranged on a pipeline between the ventilation system and the back pressure valve, and the radioactivity monitor interlocks the isolation valve and the compressor.
8. The radioactive exhaust treatment device according to claim 6, wherein the emission filter is of a vertical cylindrical shape and is filled with glass fibers.
9. The radioactive exhaust gas treatment device according to claim 1, wherein a nitrogen purge line is connected to each of a line between the radioactive exhaust gas source and the buffer tank, and a line between the gas-water separator and the guard bed.
10. The radioactive waste gas treatment device according to any one of claims 1 to 9, wherein the delay means comprises at least two column containers connected in series or in parallel by a pipeline and a valve and provided redundantly.
CN202122280012.2U 2021-09-18 2021-09-18 Radioactive waste gas treatment device Active CN216311363U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202122280012.2U CN216311363U (en) 2021-09-18 2021-09-18 Radioactive waste gas treatment device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202122280012.2U CN216311363U (en) 2021-09-18 2021-09-18 Radioactive waste gas treatment device

Publications (1)

Publication Number Publication Date
CN216311363U true CN216311363U (en) 2022-04-15

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Family Applications (1)

Application Number Title Priority Date Filing Date
CN202122280012.2U Active CN216311363U (en) 2021-09-18 2021-09-18 Radioactive waste gas treatment device

Country Status (1)

Country Link
CN (1) CN216311363U (en)

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