CN215996157U - Portable high temperature and high humidity radioactive pollution gas emergency treatment device - Google Patents
Portable high temperature and high humidity radioactive pollution gas emergency treatment device Download PDFInfo
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- CN215996157U CN215996157U CN202121345992.3U CN202121345992U CN215996157U CN 215996157 U CN215996157 U CN 215996157U CN 202121345992 U CN202121345992 U CN 202121345992U CN 215996157 U CN215996157 U CN 215996157U
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Abstract
The utility model discloses a mobile high-temperature high-humidity radioactive polluted gas emergency treatment device which comprises an air inlet, a heat exchange and dehumidification unit, a set A and a set B of nuclear grade air filtering and adsorbing units, a power unit, an auxiliary matching unit and an air outlet. The device can be arranged on an automobile base provided with a diesel generator set to move, and is transported to a site where sudden harmful gas leakage occurs according to use requirements, and radioactive gas with the temperature of less than or equal to 60 ℃ and the RH of less than or equal to 98% is treated in a staged and multi-link mode. The device is suitable for nuclear facilities, operating units, army and other nuclear-involved places to protect the health and safety of emergency personnel under the condition of nuclear accidents.
Description
Technical Field
The utility model relates to the technical field of polluted gas treatment, in particular to a high-temperature high-humidity radioactive gas treatment device which can efficiently and reliably treat high-temperature high-humidity radioactive gas, and specifically relates to a mobile high-temperature high-humidity radioactive gas treatment device which is provided with double backup filters and can be replaced on line.
Background
The radioactive gas purification process is complex and has more subsystems, which mainly comprises the following steps: an airlift exhaust system, a sump exhaust system, a shear dissolution exhaust system, and a mid-bleed evaporative exhaust system. The conventional radioactive gas purification process is as follows: and the radioactive gas sequentially enters the leaching tower, the catcher, the middle-effect filter and the high-efficiency filter for purification, is pumped out by a fan or an air compressing ejector and is discharged from a chimney at high altitude. Practice proves that the conventional radioactive gas purification process has poor radioactive gas purification effect, and has the adverse effects that high-temperature and high-humidity aerosol blocks a filter element, water vapor damages the filter element to cause the emission of airborne effluents and the like; in addition, when the activity of alpha, beta and gamma is abnormally increased or exceeds the standard, the process system can only adopt the method of emergency shutdown of the system and massive replacement of the filter core so as to avoid the pollution to the environment.
SUMMERY OF THE UTILITY MODEL
The utility model aims to solve the defects in the prior art and provides a mobile high-temperature high-humidity radioactive gas treatment device.
In order to achieve the purpose, the technical scheme of the utility model is as follows: the device comprises an air inlet, a heat exchange and dehumidification unit, a set of nuclear-grade air filtration and adsorption units A, a set of nuclear-grade air filtration and adsorption units B, a power unit, an auxiliary matching unit and an air outlet. The heat exchange and dehumidification unit comprises a primary double-sided split-flow type cooling device, a spiral efficient separator, a secondary double-sided split-flow type cooling device, a super-spiral efficient gas-liquid separator, a condensate collecting box, a plate-fin heat pipe heating device and corresponding pipeline valves; the auxiliary matching unit comprises a PLC controller and a noise reduction, silencing and heat preservation shelter; the air inlet is connected with the first-stage double-sided shunting type cooling device through a pipeline; the nuclear-grade air filtering and adsorbing unit comprises a coarse filter, a reusable nuclear-grade efficient filter, a nuclide catcher and a differential pressure gauge, and a valve for controlling air intake is arranged on a pipeline, which is connected with the plate-fin heat pipe heating device and the nuclear-grade air filtering and adsorbing unit; a radioactive gas detection probe connected with a control cabinet is mounted at an air outlet of the nuclear-grade air filtering and adsorbing unit, a PLC (programmable logic controller) is mounted in the control cabinet, and the differential pressure gauge and the radioactive gas detection probe are connected with the PLC and transmit signals to the PLC, so that intelligent control is realized; the power unit is a centrifugal fan, and a valve for controlling air outlet is arranged on a pipeline which is connected with the centrifugal fan and the nuclear-grade air filtering and adsorbing unit.
The heat exchange dehumidification unit, the A set and the B set of nuclear grade air filtration adsorption unit, the power unit and the control cabinet are sequentially installed inside the noise reduction and silencing cabin, all parts are seamlessly and fully welded, and no leakage point is ensured.
Compared with the prior art, the utility model has the following beneficial effects: this processing apparatus cools down, dehumidifies radioactive gas through heat transfer dehumidification unit earlier, has improved the filtration efficiency of filter core, has prolonged the life of filter core, has solved the easy filter core that blocks up of aerosol, steam and has destroyed the filter core scheduling problem, has improved the reliability of filtration efficiency and device, has better economic value. The device comprises two sets of nuclear-grade air filtering units which are mutually backed up and matched for use, can realize the online replacement of the double backups of the filter, can ensure long-time use, can automatically detect the system sealing, avoids diffusion pollution and has better safety benefit.
Drawings
FIG. 1 is a schematic view of the structure of the present invention.
In the figure: 1-an air inlet; 2-first-stage double-sided shunting type cooling device; 3-a vortex high-efficiency separator; 4-a two-stage double-sided split-flow cooling device; 5-super-cyclone high-efficiency gas-liquid separator; 6-a condensate collection tank; 7-a plate-fin heat pipe heating device; 8-coarse filter (A); 9-reusable nuclear grade high efficiency filter (A); 10-nuclide trap (A); 11-differential pressure gauge (A); 12-radioactive gas detection probe (a); 13-coarse filter (B); 14-reusable nuclear grade high efficiency filter (B); 15-nuclide trap (B); 16-differential pressure gauge (B); 17-radioactive gas detection probe (B); 18-25-pipeline valve switch; 26-a centrifugal fan; 27-a PLC controller; 28-noise reduction, noise reduction and heat preservation shelter; 29-air outlet.
Detailed Description
As shown in figure 1, the movable high-temperature high-humidity radioactive polluted gas emergency treatment device comprises an air inlet (1), heat exchange dehumidification units (2-7), nuclear-grade air filtration adsorption units (totally two sets of nuclear-grade air filtration adsorption units, 8-11 sets of nuclear-grade air filtration adsorption units, 13-16 sets of nuclear-grade air filtration adsorption units, a power unit and auxiliary matching units (27, 28) and an air outlet (29), wherein the above functional units are sequentially connected and are all borne on the auxiliary matching unit noise reduction and noise reduction heat preservation shelter (28).
Further, the heat exchange and dehumidification unit comprises a first-stage double-sided split-flow type cooling device (2), a spiral efficient separator (3), a second-stage double-sided split-flow type cooling device (4), a super-spiral efficient gas-liquid separator (5), a condensate collecting box (6), a plate-fin type heat pipe heating device (7) and a corresponding pipeline valve.
Further, the plate-fin heat pipe temperature raising device (7) is connected with a nuclear-grade air filtering and adsorbing unit through a pipeline, and the nuclear-grade air filtering and adsorbing unit comprises coarse filters (8 and 13), reusable nuclear-grade high-efficiency filters (9 and 14), nuclide traps (10 and 15) and differential pressure meters (11 and 16); the radioactive gas detection probes (12 and 17) connected with the control cabinet are installed at the gas outlet of the filtering device, the PLC (27) is installed in the control cabinet, the differential pressure meters (11 and 16) and the radioactive gas detection probes (12 and 17) are connected with the PLC (27), signals are transmitted to the PLC (27), and intelligent control is achieved.
Further, the power unit is a centrifugal fan (26) which provides the original power for the operation of the device.
Furthermore, the heat exchange and dehumidification system also comprises a noise reduction and silencing heat preservation shelter (28), wherein the heat exchange and dehumidification unit, the A set and the B set of nuclear grade air filtration and adsorption unit, the power unit and the control cabinet are sequentially connected and are respectively borne on the noise reduction and silencing heat preservation shelter in a bolt fixing or welding mode.
The operation process of the utility model is as follows: 1. exhaust air passes through the air inlet (1) and the primary double-sided split-flow cooling device (2) to condense water vapor; then the gaseous humid air and the condensed water are separated by a spiral high-efficiency separator (3); then the wet air is dehumidified by a secondary double-sided shunting type cooling device (4); then the condensed water carried in the gaseous humid air is further removed by a super-rotary high-efficiency gas-liquid separator (5); and finally, the temperature is raised through a plate-fin heat pipe temperature raising device (7), so that the relative humidity of the exhaust air is further reduced, a subsequent reusable nuclear-grade high-efficiency filter is protected to the maximum extent, and the good working environment of the filter is ensured.
2. The exhaust air treated by the heat exchange and dehumidification unit enters an air filtering unit, the exhaust air firstly enters a coarse filter (8) to primarily filter aerosol, dust and particles contained in the entering air, the filtering efficiency is improved, the exhaust air passes through a reusable nuclear-grade high-efficiency filter (9) to precisely filter the entering air, and then the exhaust air passes through a nuclide catcher (10) to adsorb methyl iodide and iodine vapor in the air, so that the radioactivity of the air is thoroughly removed.
3. The treated gas is discharged into the atmosphere through an exhaust port (29).
The filter dual backup scheme is as follows: 1. and the data measured by the probe is transmitted to the control module, if the air outlet of the A set of nuclear-grade air filtering and adsorbing units does not meet the emission standard, the two-stage filtering systems work in series, and the gas enters the B set of nuclear-grade air filtering and adsorbing units for secondary filtering. If the air outlet of the A set of nuclear-grade air filtering and adsorbing units reaches the discharge standard, the two stages of filtering units work in parallel, and the working efficiency is increased.
2. Considering that the service time of the target device is uncertain, the air purification module adopts a mode of switching the use of the nuclear-grade air filtration unit dual systems, when the pressure difference of the A set of nuclear-grade air filtration adsorption units gives an alarm, the A set of nuclear-grade air filtration adsorption unit pipeline valves 18 and 24 are closed, the A set of nuclear-grade air filtration adsorption unit pipeline valves are opened 19 and 25, the B set of nuclear-grade air filtration adsorption units are started, and a worker replaces the filtering components in the A set of nuclear-grade air filtration adsorption units. And after the pressure difference of the B set of nuclear-grade air filtering and adsorbing units gives an alarm, the B set of nuclear-grade air filtering and adsorbing units 19 and 25 are closed, 18 and 24 are opened, the A set of nuclear-grade air filtering and adsorbing units are started, and the steps are repeated.
3. When the radiation probe (12) in the A set of nuclear-grade air filtering and adsorbing unit senses that the filtered air cannot meet the emission requirement, 24 is closed, 21, 22 and 25 are opened, the A set of nuclear-grade air filtering and adsorbing unit is automatically connected with the B set of nuclear-grade air filtering and adsorbing unit in series, the A set of nuclear-grade air filtering and adsorbing unit is detected to be qualified by the radiation probe (17) of the B set of nuclear-grade air filtering and adsorbing unit and then is discharged to the atmosphere, the A set of nuclear-grade air filtering and adsorbing unit is opened, 18, 21 and 22 are closed, and the B set of nuclear-grade air filtering and adsorbing unit can normally work. If the B set of nuclear grade air filtration and adsorption units meet the A set of nuclear grade air filtration and adsorption units, the operation is the same as the operation. Two sets of nuclear grade air filtration adsorption units which are mutually standby are matched for use, so that air filtration can be ensured to be used for a long time, the system can be automatically detected to be sealed, and diffusion pollution is avoided.
The foregoing shows and describes the general principles, essential features, and advantages of the utility model. It will be understood by those skilled in the art that the present invention is not limited to the embodiments described above, which are merely illustrative of the principles of the utility model, but that various changes and modifications may be made without departing from the spirit and scope of the utility model, which fall within the scope of the utility model as claimed. The scope of the utility model is defined by the appended claims and equivalents thereof.
Claims (2)
1. A mobile high-temperature high-humidity radioactive polluted gas emergency treatment device comprises an air inlet (1), a heat exchange and dehumidification unit, a set of nuclear-grade air filtration and adsorption units A, a set of nuclear-grade air filtration and adsorption units B, a power unit, an auxiliary matching unit and an air outlet (29); the heat exchange and dehumidification unit comprises a primary double-sided split-flow type cooling device (2), a spiral efficient separator (3), a secondary double-sided split-flow type cooling device (4), a super-spiral efficient gas-liquid separator (5), a condensate collecting box (6), a plate-fin heat pipe heating device (7) and corresponding pipeline valves, and the auxiliary matching unit comprises a PLC (programmable logic controller) and a noise reduction, silencing and heat preservation shelter (28); the air inlet (1) is connected with the primary double-sided shunting type cooling device (2) through a pipeline; the nuclear-grade air filtering and adsorbing unit comprises coarse filters (8 and 13), reusable nuclear-grade efficient filters (9 and 14), nuclide traps (10 and 15) and pressure difference meters (11 and 16), and a valve for controlling air inflow is arranged on a pipeline, connected with the nuclear-grade air filtering and adsorbing unit, of the plate-fin heat pipe heating device (7); the air outlet of the nuclear-grade air filtering and adsorbing unit is provided with radioactive gas detection probes (12 and 17) connected with the control cabinet, the control cabinet is internally provided with a PLC (programmable logic controller) controller (27), and the differential pressure meters (11 and 16) and the radioactive gas detection probes (12 and 17) are connected with the PLC controller (27) and transmit signals to the PLC controller (27) to realize intelligent control; the power unit is a centrifugal fan (26), and a valve for controlling air outlet is arranged on a pipeline connecting the centrifugal fan (26) and the nuclear-grade air filtering and adsorbing unit.
2. The mobile high-temperature high-humidity radioactive polluted gas emergency treatment device according to claim 1, wherein the whole device can be mounted on a vehicle equipped with a diesel generator set for convenient movement, and the power supply of the treatment device is provided by the diesel generator set.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202121345992.3U CN215996157U (en) | 2021-06-17 | 2021-06-17 | Portable high temperature and high humidity radioactive pollution gas emergency treatment device |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202121345992.3U CN215996157U (en) | 2021-06-17 | 2021-06-17 | Portable high temperature and high humidity radioactive pollution gas emergency treatment device |
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| CN215996157U true CN215996157U (en) | 2022-03-11 |
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| CN202121345992.3U Active CN215996157U (en) | 2021-06-17 | 2021-06-17 | Portable high temperature and high humidity radioactive pollution gas emergency treatment device |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115254811A (en) * | 2022-04-15 | 2022-11-01 | 中国辐射防护研究院 | Cleaning and dust collecting device for radioactive loose pollutants in high-temperature gas cooled reactor loop pipeline |
-
2021
- 2021-06-17 CN CN202121345992.3U patent/CN215996157U/en active Active
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115254811A (en) * | 2022-04-15 | 2022-11-01 | 中国辐射防护研究院 | Cleaning and dust collecting device for radioactive loose pollutants in high-temperature gas cooled reactor loop pipeline |
| CN115254811B (en) * | 2022-04-15 | 2023-06-16 | 中国辐射防护研究院 | High-temperature gas cooled reactor loop pipeline radioactive loose pollutant cleaning and dust collecting device |
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