CN112717625A - Hydrogen-containing waste gas treatment system of nuclear power station - Google Patents
Hydrogen-containing waste gas treatment system of nuclear power station Download PDFInfo
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- CN112717625A CN112717625A CN202011322858.1A CN202011322858A CN112717625A CN 112717625 A CN112717625 A CN 112717625A CN 202011322858 A CN202011322858 A CN 202011322858A CN 112717625 A CN112717625 A CN 112717625A
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- 239000001257 hydrogen Substances 0.000 title claims abstract description 126
- 229910052739 hydrogen Inorganic materials 0.000 title claims abstract description 126
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 title claims abstract description 124
- 239000002912 waste gas Substances 0.000 title claims abstract description 124
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims abstract description 183
- 239000007789 gas Substances 0.000 claims abstract description 73
- 229910052799 carbon Inorganic materials 0.000 claims abstract description 51
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N Silicium dioxide Chemical compound O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 claims abstract description 43
- 239000000741 silica gel Substances 0.000 claims abstract description 43
- 229910002027 silica gel Inorganic materials 0.000 claims abstract description 43
- 230000014759 maintenance of location Effects 0.000 claims abstract description 39
- 238000009423 ventilation Methods 0.000 claims abstract description 30
- 230000001105 regulatory effect Effects 0.000 claims abstract description 29
- 238000001035 drying Methods 0.000 claims abstract description 14
- 238000012544 monitoring process Methods 0.000 claims abstract description 13
- 239000002245 particle Substances 0.000 claims description 33
- 238000005070 sampling Methods 0.000 claims description 13
- 238000005192 partition Methods 0.000 claims description 12
- 239000012465 retentate Substances 0.000 claims description 10
- 238000011144 upstream manufacturing Methods 0.000 claims description 8
- 230000008929 regeneration Effects 0.000 claims description 7
- 238000011069 regeneration method Methods 0.000 claims description 7
- 230000000717 retained effect Effects 0.000 claims description 6
- 230000033228 biological regulation Effects 0.000 claims description 5
- 238000001816 cooling Methods 0.000 claims description 5
- 238000007599 discharging Methods 0.000 claims description 5
- 230000001172 regenerating effect Effects 0.000 claims description 2
- 230000002285 radioactive effect Effects 0.000 abstract description 25
- 238000001514 detection method Methods 0.000 abstract description 4
- 150000002431 hydrogen Chemical class 0.000 abstract description 2
- 238000007781 pre-processing Methods 0.000 abstract description 2
- 229910052743 krypton Inorganic materials 0.000 description 11
- 229910052724 xenon Inorganic materials 0.000 description 11
- DNNSSWSSYDEUBZ-UHFFFAOYSA-N krypton atom Chemical compound [Kr] DNNSSWSSYDEUBZ-UHFFFAOYSA-N 0.000 description 10
- FHNFHKCVQCLJFQ-UHFFFAOYSA-N xenon atom Chemical compound [Xe] FHNFHKCVQCLJFQ-UHFFFAOYSA-N 0.000 description 10
- 238000001179 sorption measurement Methods 0.000 description 9
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 8
- 238000013461 design Methods 0.000 description 7
- 238000000034 method Methods 0.000 description 7
- 238000012545 processing Methods 0.000 description 7
- 230000008569 process Effects 0.000 description 5
- 238000012423 maintenance Methods 0.000 description 4
- 239000002901 radioactive waste Substances 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 description 2
- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 description 2
- 229910002092 carbon dioxide Inorganic materials 0.000 description 2
- 238000003795 desorption Methods 0.000 description 2
- 239000011261 inert gas Substances 0.000 description 2
- 239000011148 porous material Substances 0.000 description 2
- 230000009467 reduction Effects 0.000 description 2
- 238000010521 absorption reaction Methods 0.000 description 1
- 230000004913 activation Effects 0.000 description 1
- 239000001569 carbon dioxide Substances 0.000 description 1
- 239000012159 carrier gas Substances 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 230000003749 cleanliness Effects 0.000 description 1
- 230000006837 decompression Effects 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 238000007791 dehumidification Methods 0.000 description 1
- 230000009977 dual effect Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 229910052757 nitrogen Inorganic materials 0.000 description 1
- 230000002035 prolonged effect Effects 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01D—SEPARATION
- B01D53/00—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols
- B01D53/02—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols by adsorption, e.g. preparative gas chromatography
- B01D53/04—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols by adsorption, e.g. preparative gas chromatography with stationary adsorbents
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01D—SEPARATION
- B01D53/00—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols
- B01D53/26—Drying gases or vapours
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/02—Treating gases
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01D—SEPARATION
- B01D2256/00—Main component in the product gas stream after treatment
- B01D2256/16—Hydrogen
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- Chemical & Material Sciences (AREA)
- Engineering & Computer Science (AREA)
- Analytical Chemistry (AREA)
- General Chemical & Material Sciences (AREA)
- Oil, Petroleum & Natural Gas (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Treating Waste Gases (AREA)
Abstract
The invention belongs to the technical field of a waste gas treatment system of a nuclear power station, and particularly relates to a hydrogen-containing waste gas treatment system of the nuclear power station. In this hydrogen-containing exhaust gas treatment system of nuclear power station: the pretreatment unit comprises a pressure regulating valve and a silica gel dryer; the outlet of the pre-dryer is connected with the inlet of the pressure regulating valve, and the outlet of the pressure regulating valve is connected with the inlet of the silica gel dryer; the treatment unit comprises an activated carbon retention bed; the active carbon detention bed is connected with a silica gel dryer; the emission detection unit comprises a ventilation device and a radioactivity monitor; the waste gas that nuclear power station exhaust system discharged carries out depressurization pressure regulating and drying process through the preprocessing unit after, detains radioactive gas through the active carbon detention bed and decays after, and the rethread monitoring discharge unit will be monitored the qualified waste gas of ware and discharge in the external environment. According to the invention, a high-pressure storage tank is not required, leakage of the hydrogen-containing waste gas of the nuclear power station due to long-time high-pressure storage is avoided, and the safety of radioactive gas emission is improved.
Description
Technical Field
The invention belongs to the technical field of a waste gas treatment system of a nuclear power station, and particularly relates to a hydrogen-containing waste gas treatment system of the nuclear power station.
Background
During normal operation and expected operation of a nuclear power plant, hydrogen-containing waste gas with radioactivity is inevitably generated. The hydrogen-containing waste gas mainly comprises hydrogen produced by nuclear fission reaction, radioactive inert gases such as krypton and xenon. In order to meet the national demand for the emission of hydrogen-containing waste gas from nuclear power plants, the radioactive hydrogen-containing waste gas cannot be directly emitted into the air, so as to avoid destroying the natural ecosystem.
In the prior art, a method for treating hydrogen-containing waste gas of a nuclear power plant generally includes collecting radioactive hydrogen-containing waste gas discharged by an upstream nuclear auxiliary system, storing the radioactive hydrogen-containing waste gas in a decay tank after pressurization treatment, and discharging the radioactive hydrogen-containing waste gas to the environment after decay for a period of time. However, the method for storing and discharging the waste gas in the decay tank has high requirement on the pressure of the decay tank, long storage time and potential risk of leakage of the hydrogen-containing waste gas to the environment; and operations such as air inlet, switching, closing, air exhaust and the like are required to be performed on the decay tank manually, and the operation and maintenance work is complex and high in cost.
Disclosure of Invention
The invention provides a system for treating hydrogen-containing waste gas of a nuclear power station, aiming at solving the problems of potential leakage risk and the like of treating the hydrogen-containing waste gas by a decay tank of the nuclear power station in the prior art.
In view of the above problems, an embodiment of the present invention provides a system for treating hydrogen-containing waste gas from a nuclear power plant, including:
the pretreatment unit comprises a pressure regulating valve for regulating the pressure of the hydrogen-containing waste gas of the nuclear power station and a silica gel dryer for dehumidifying the hydrogen-containing waste gas of the nuclear power station; the inlet of the pressure regulating valve is connected with the outlet of a compressor of a hydrogen-containing waste gas system of the nuclear power station, and the outlet of the pressure regulating valve is connected with the inlet of the silica gel dryer;
a treatment unit comprising a retentate bed of activated carbon; the inlet of the active carbon retention bed is connected with the outlet of the silica gel dryer;
the monitoring and discharging unit comprises a ventilation device communicated with the external environment and a radioactivity monitor installed on the ventilation device; the inlet of the ventilation device is connected with the outlet of the active carbon retention bed;
after the hydrogen-containing waste gas discharged by the exhaust system of the nuclear power station is subjected to pressure regulation and drying treatment by the pretreatment unit, the hydrogen-containing waste gas flows into the treatment unit and is retained and decayed by the activated carbon retention bed, and qualified waste gas monitored by the radioactivity monitor is discharged into the external environment by the monitoring discharge unit.
Optionally, the pretreatment unit further comprises a pre-dryer for cooling and dehumidifying the hydrogen-containing waste gas of the nuclear power plant; and the inlet of the pressure regulating valve is connected with the outlet of a compressor of a hydrogen-containing waste gas system of the nuclear power station through the pre-dryer.
Optionally, a condensate collecting pipe is arranged on the pre-dryer; the pretreatment unit also comprises a condensate collection tank communicated with the outlet of the condensate collection pipe.
Optionally, the pretreatment unit further comprises a regeneration heater for performing regeneration treatment on the silica gel dryer.
Optionally, the treatment unit comprises a cylinder for mounting the retentate bed, the activated carbon retentate bed comprising a partition and first and second layered carbon beds connected on opposite sides of the partition; the first layered carbon bed and the second layered carbon bed are arranged along the axial direction of the cylinder and are filled with activated carbon particles; the inlet of the cylinder is connected with the outlet of the silica gel dryer, and the outlet of the cylinder is communicated with the ventilation device.
Optionally, the first layered carbon bed comprises at least two first semicircular bearing plates arranged at intervals along the axial direction of the cylinder, and the second layered carbon bed comprises at least two second semicircular bearing plates arranged at intervals along the axial direction of the cylinder; and each first semicircular bearing plate and each second semicircular bearing plate are filled with the activated carbon particles.
Optionally, the treatment unit further comprises a spreader for lifting the active retention bed from within the cartridge.
Optionally, the cylinder is further provided with an upstream gas sampling port and a downstream gas sampling port, the upstream gas sampling port is arranged at an inlet of the cylinder, and the downstream gas sampling port is arranged at an outlet of the cylinder.
Optionally, the monitoring emission unit further comprises a gas filter and an emission control valve; the inlet of the gas filter is communicated with the outlet of the activated carbon retention bed, the outlet of the gas filter is communicated with the inlet of the radioactivity detector, and the radioactivity detector is communicated with the inlet of the ventilation device through a quick discharge control valve.
Optionally, the hydrogen-containing waste gas treatment system of the nuclear power plant further comprises a return pipe, and the emission control valve comprises a first outlet and a second outlet; the first outlet of the discharge control valve is communicated with the inlet of the ventilation device, and the second outlet of the discharge control valve is communicated with the inlet of the pressure regulating valve through the return pipe. The hydrogen-containing waste gas treatment system of the nuclear power station comprises a pretreatment unit, a treatment unit and a monitoring discharge unit which are connected in sequence; hydrogen-containing waste gas discharged by a nuclear power station firstly enters the pretreatment unit, is subjected to dehumidification and cooling treatment by the predryer in the pretreatment unit, is subjected to pressure regulation by the pressure regulating valve and then enters the silica gel dryer for drying; hydrogen-containing waste gas of the nuclear power station is input into the activated carbon retention bed, and radioactive gases of krypton and xenon in the waste gas are adsorbed in pores of activated carbon by activated carbon particles in the activated carbon retention bed, so that the radioactive gases of krypton and xenon decay for a long time; the gas molecules in the air flow out of the active carbon pores under the impact of the gas molecules in the air flow and are adsorbed by the next active carbon particles to form a long-time process of adsorption-desorption-re-adsorption-re-desorption until the gas flows downstream to the monitoring and discharging unit, the radioactivity of the gas decays to a very low level (meeting the discharge), and finally the gas is discharged into the external environment through the ventilation device after the gas molecules are detected to be qualified by the radioactivity monitor. According to the system for treating the hydrogen-containing waste gas of the nuclear power station, the characteristic that the active carbon particles subjected to hardening and surface activation treatment in the active carbon detention bed have adsorption capacity on radioactive carrier gases krypton and xenon in the hydrogen-containing waste gas of the nuclear power station is utilized, the treatment efficiency of the hydrogen-containing waste gas of the nuclear power station is improved, meanwhile, a high-pressure storage tank is not needed, the storage time of the hydrogen-containing waste gas of the nuclear power station is effectively shortened, the hydrogen-containing waste gas of the nuclear power station is prevented from being leaked due to long-time high-pressure storage, and the safety of radioactive gas emission is improved.
Drawings
The invention is further illustrated with reference to the following figures and examples.
Fig. 1 is a schematic structural diagram of a hydrogen-containing waste gas treatment system of a nuclear power plant according to an embodiment of the present invention;
FIG. 2 is a schematic structural diagram of a hydrogen-containing waste gas treatment system of a nuclear power plant according to another embodiment of the present invention;
FIG. 3 is a sectional view of an activated carbon retention bed installed in a cylinder of a hydrogen-containing waste gas treatment system of a nuclear power plant according to another embodiment of the present invention;
FIG. 4 is a top view of an activated carbon retention bed installed in a barrel of a hydrogen-containing waste gas treatment system of a nuclear power plant according to another embodiment of the present invention;
FIG. 5 is a top view of an activated carbon retention bed of a hydrogen-containing waste gas treatment system of a nuclear power plant according to another embodiment of the present invention;
FIG. 6 is a schematic structural diagram of an activated carbon retention bed of a hydrogen-containing waste gas treatment system of a nuclear power plant according to another embodiment of the invention;
FIG. 7 is a front view of a silica gel dryer of a hydrogen-containing waste gas treatment system of a nuclear power plant according to another embodiment of the present invention;
fig. 8 is a top view of a silica gel dryer of a hydrogen-containing off-gas treatment system of a nuclear power plant according to another embodiment of the present invention.
The reference numerals in the specification are as follows:
1. a pre-processing unit; 11. a pressure regulating valve; 12. a silica gel dryer; 121. a cylindrical column; 1211. a support arm; 1212. an upper flange; 1213. a lower flange; 122. a silica gel drying bed; 13. a pre-dryer; 14. a condensate collection tank; 15. a regenerative heater; 2. a processing unit; 21. an activated carbon retention bed; 211. a partition plate; 212. a first layered carbon bed; 2121. a first semicircular bearing plate; 213. a second layered carbon bed; 2131. a second semicircular bearing plate; 214. activated carbon particles; 22. a barrel; 221. an upstream gas sampling port; 3. an emission detection unit; 31. a ventilation device; 32. a radioactivity monitor; 33. a gas filter; 34. an exhaust control valve; 4. a return pipe.
Detailed Description
In order to make the technical problems, technical solutions and advantageous effects solved by the present invention more clearly apparent, the present invention is further described in detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the invention and are not intended to limit the invention.
It is to be understood that the terms "upper", "lower", "left", "right", "front", "rear", "middle", and the like, indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings, are only for convenience in describing the present invention and simplifying the description, and do not indicate or imply that the device or element referred to must have a particular orientation, be constructed in a particular orientation, and be operated, and thus, should not be construed as limiting the present invention.
As shown in fig. 1, an embodiment of the present invention provides a system for treating hydrogen-containing waste gas from a nuclear power plant, including:
the device comprises a pretreatment unit 1, wherein the pretreatment unit 1 comprises a pressure regulating valve 11 for regulating the pressure of hydrogen-containing waste gas of the nuclear power station, and a silica gel dryer 12 for dehumidifying the hydrogen-containing waste gas of the nuclear power station; the inlet of the pressure regulating valve 11 is connected with the outlet of a compressor of a hydrogen-containing waste gas system of the nuclear power station, and the outlet of the pressure regulating valve 11 is connected with the inlet of the silica gel dryer 12; it is understood that, in order to ensure the adsorption capacity of the activated carbon particles 214 in the activated carbon retention bed 21, the silica gel dryer 12 is required to dehumidify the hydrogen-containing waste gas from the nuclear power plant and the pressure regulating valve 11 is required to regulate the pressure of the hydrogen-containing waste gas from the nuclear power plant before the hydrogen-containing waste gas from the nuclear power plant enters the activated carbon retention bed 21. Further, because the silica gel on the silica gel dryer 12 can be in a loose state, in order to avoid that the silica gel in the silica gel dryer 12 is washed away by the high-pressure hydrogen-containing waste gas discharged from the outlet of the compressor of the hydrogen-containing waste gas system in the nuclear power station, the hydrogen-containing waste gas in the nuclear power station needs to be subjected to pressure reduction through the pressure regulating valve 11 and then to be dried by the silica gel dryer 12.
A treatment unit 2, said treatment unit 2 comprising a bed 21 of activated carbon retentate; the inlet of the active carbon retention bed 21 is connected with the outlet of the silica gel dryer 12; as can be appreciated, the activated carbon particles 214 in the activated carbon retentate bed 21 can adsorb nuclear powerThe radioactive gas such as Kr and Xe in the hydrogen-containing waste gas of the station, but non-radioactive H2、N2、CO2The gas may be passed directly through the activated carbon particles 214.
A monitoring emission unit 3, the monitoring emission unit 3 including a ventilation device communicating with an external environment, and a radioactivity monitor 32 mounted on the ventilation device; the inlet of the ventilation device is connected with the outlet of the active carbon retention bed 21; preferably, the radioactivity monitor 32 is a beta sensitive detector, which can be used to monitor the activity concentration of the radioactive gas after adsorption through the retention bed. It will be appreciated that in order to ensure the level of radioactivity in the hydrogen-containing waste gas from the nuclear power plant that is discharged from the ventilation unit to the environment, it is necessary to say that the radioactivity monitor 32 detects that it is within standards before it is discharged. The dual in-line two-level threshold design of the radioactivity monitor 32 further ensures that the exhaust emitted to the environment is of a standard (low radioactivity) emission.
It is understood that the pretreatment unit 1, the treatment unit 2, and the detection and discharge unit are connected by an exhaust pipe.
After the exhaust gas discharged from the exhaust system of the nuclear power station is subjected to pressure regulation and drying treatment by the pretreatment unit 1, the exhaust gas flows into the treatment unit 2 and is retained and decayed by the activated carbon retention bed 21, and qualified exhaust gas monitored by the radioactivity monitor 32 is discharged into the external environment through the detection discharge unit.
In the invention, the hydrogen-containing waste gas treatment system of the nuclear power station comprises a pretreatment unit 1, a treatment unit 2 and a radioactivity monitor 32 which are connected in sequence; the exhaust gas discharged by the nuclear power station firstly enters the pretreatment unit 1, enters the pressure regulating valve 11 for pressure regulation, then enters the silica gel dryer 12 for drying, then the hydrogen-containing exhaust gas of the nuclear power station is input into the activated carbon retention bed 21, and is adsorbed and decayed by the activated carbon particles 214 in the activated carbon retention bed 21, and finally the hydrogen-containing exhaust gas of the nuclear power station is detected by the radioactivity monitor 32 to be qualified and then is discharged into the external environment by the ventilation device. In the system for treating the hydrogen-containing waste gas of the nuclear power station, the characteristic that the active carbon particles 214 in the active carbon detention bed 21 adsorb the radioactive inert gases krypton and xenon in the hydrogen-containing waste gas of the nuclear power station is utilized, the treatment efficiency of the hydrogen-containing waste gas of the nuclear power station is improved, meanwhile, a high-pressure storage tank is not needed, the storage time of the hydrogen-containing waste gas of the nuclear power station is effectively shortened, the problem that the hydrogen-containing waste gas of the nuclear power station is leaked due to long-time high-pressure storage is avoided, and the safety of radioactive gas emission is improved.
In one implementation, as shown in fig. 7 and 8, the silica gel dryer 12 includes a cylindrical column 121 and a silica gel drying bed 122 installed in the cylindrical column 121; the outer wall of the cylindrical column 121 is further provided with a support arm 1211 for supporting the cylindrical column 121; an upper flange 1212 and a lower flange 1213 are respectively mounted at the upper and lower ports of the cylindrical column 121; silica gel particles for adsorbing water in the hydrogen-containing waste gas of the nuclear power station are arranged on the silica gel drying bed 122. The silica gel dryer 12 is simple in structure and convenient to install and maintain.
In one implementation, as shown in fig. 1, the pretreatment unit 1 further includes a pre-dryer 13 for performing cooling and dehumidifying treatment on the hydrogen-containing waste gas of the nuclear power plant; the inlet of the pressure regulating valve 11 is connected with the outlet of a compressor of a hydrogen-containing waste gas system of the nuclear power station through the pre-dryer 13. It is understood that, in order to ensure the drying capability of the silica gel in the silica gel drying bed 122 and the adsorption capability of the activated carbon particles 214 in the activated carbon retention bed 21, the pre-dryer 13 is required to cool and dehumidify the hydrogen-containing waste gas from the nuclear power plant before the hydrogen-containing waste gas enters the silica gel drying bed 122. Further, the temperature and humidity of the exhaust gas discharged by the exhaust system of the nuclear power plant are relatively high, and the hydrogen-containing exhaust gas of the nuclear power plant needs to be subjected to cooling and dehumidifying treatment by the pre-dryer 13; pass through after pressure regulating valve 11 carries out the pressure reduction treatment, process the hydrogenous waste gas of nuclear power station after the predryer 13 handles still has certain humidity, warp the hydrogenous waste gas of nuclear power station after the predryer 13 handles gets into after the decompression silica gel desicator 12, and by further drying process is carried out to the hydrogenous waste gas of nuclear power station to silica gel desicator 12, just can guarantee to get into the hydrogenous waste gas radioactive gas of nuclear power station of active carbon detention bed 21 adsorbs krypton and xenon ability. In the invention, the design of the pre-dryer and the silica gel dryer 12 improves the service life of the activated carbon particles 214 in the activated carbon retention bed 21, improves the treatment efficiency of the hydrogen-containing waste gas treatment system of the nuclear power station on the hydrogen-containing waste gas of the nuclear power station, and improves the redundancy safety of the system.
In one embodiment, as shown in fig. 2, the gas dryer is provided with a condensate header; the pre-dryer 13 also comprises a condensate collection tank 14 communicating with the outlet of the condensate collection header. It is understood that the hydrogen-containing waste gas of the nuclear power plant is firstly cooled by the pre-dryer 13, after the water vapor in the waste gas is condensed and dehumidified, the pre-dryer 13 removes a large amount of water in the hydrogen-containing waste gas of the nuclear power plant, and the water absorbed by the pre-dryer 13 is discharged into the condensate collecting tank 14 through the condensate collecting pipe. Preferably, the outlet of the condensate collection tank 14 is connected to the nuclear power plant drain by a trap. It can be understood that when the height of the water surface in the condensate collection tank 14 reaches a preset liquid level, the drain valve is opened, and the water in the condensate collection tank 14 can be automatically drained to a drain pipe of the nuclear power plant; when the level of the water in the condensate collection tank 14 is lower than a preset level, the trap is closed. In the invention, the design of the condensate collecting box 14 improves the efficiency of the gas dryer for drying the hydrogen-containing waste gas of the nuclear power station, and reduces the workload of the nuclear power station maintainers.
In an embodiment, as shown in fig. 2, the pretreatment unit 1 further comprises a regeneration heater 15 for performing a regeneration process on the silica gel dryer 12. It can be understood that, during the overhaul of the nuclear power plant, the regeneration heating device can perform online regeneration on the adsorption capacity of the silica gel in the silica gel dryer 12, so that the water absorption capacity of the silica gel dryer 12 can be recovered, and the treatment efficiency of the hydrogen-containing waste gas treatment system of the nuclear power plant on the hydrogen-containing waste gas of the nuclear power plant is further improved.
In one embodiment, as shown in fig. 3 to 6, the treatment unit 2 comprises a cylinder 22 for mounting the retentate bed, the activated carbon retentate bed 21 comprises a partition 211 and a first and a second layered carbon bed 212, 213 connected on opposite sides of the partition 211; the first layered carbon bed 212 and the second layered carbon bed 213 are arranged along the axial direction of the cylinder 22 and are filled with activated carbon particles 214; the inlet of the cylinder 22 is communicated with the pressure regulating valve 11, and the outlet of the cylinder 22 is communicated with the ventilation device. It can be understood that, preferably, the diameter of the activated carbon particles 214 ranges from 3 mm to 5mm, such as 3.5mm, 4mm, 4.5mm, etc.; it is understood that the diameter of the activated carbon particles 214 can be set to other values according to actual requirements, such as 6mm, 7mm, etc., and the activated carbon particles 214 need to be hardened and activated to have good krypton and xenon adsorbing function (i.e. the activated carbon particles 214 installed on the activated carbon retention bed 21 need to be hardened and activated).
Specifically, radioactive waste gas discharged from the nuclear power plant enters the first layered carbon bed 212 from the inlet of the barrel 22, and passes through the adsorption of the activated carbon particles 214 on the first layered carbon bed 212; then enters the second layered carbon bed, is adsorbed by the activated carbon particles 214 in the second layered carbon bed, and is discharged into a ventilation device through an outlet of the cylinder 22 and is discharged into the external environment through the ventilation device; wherein, the main radioactive gases krypton and xenon in the hydrogen-containing waste gas of the nuclear power plant need to pass through the processes of adsorption-desorption-re-adsorption-re-desorption of the activated carbon particles 214 in the first layered carbon bed 212 and the second layered carbon bed, so that the main radioactive gases krypton and xenon in the radioactive waste gas of the nuclear power plant are retained in the activated carbon particles 214 for a long time to decay, and finally the amount of radioactive content in the discharged hydrogen-containing waste gas of the nuclear power plant is low; the radioactive waste gas of the nuclear power station is mixed gas, wherein most of the radioactive waste gas is non-radioactive gases such as nitrogen, hydrogen, carbon dioxide and the like, the activated carbon particles 214 do not adsorb the gases, the non-radioactive gases directly pass through the activated carbon detention bed 21 and are discharged to the external environment through the ventilation device, so that only a small volume of the radioactive gases such as krypton and xenon is retained, the problems in all hydrogen-containing waste gas storage systems are solved, the treatment efficiency of the hydrogen-containing waste gas of the nuclear power station is improved, the safety of the hydrogen-containing waste gas treatment system of the nuclear power station is improved, and the cost for treating the waste gas of the nuclear power station is reduced.
In one embodiment, as shown in fig. 5 and 6, the first layered carbon bed 212 and the second layered carbon bed 213 are symmetrically disposed. Specifically, the first layered carbon bed 212 and the second layered carbon bed 213 are symmetrically disposed with respect to the partition 211. It can be understood that the first layered carbon bed 212 and the second layered carbon bed 213, which are symmetrically disposed, have a simple structure and low manufacturing cost, and also improve the adsorption efficiency of the activated carbon particles 214.
In one embodiment, as shown in FIG. 3, the processing unit 2 further includes a first flange and a second flange mounted at opposite ends of the barrel 22. Preferably, the processing unit 2 further includes a conical cylinder installed between the cylinder 22 and the second flange, and a cross-sectional area of the conical cylinder perpendicular to an axis of the cylinder 22 is gradually increased from the second flange toward the cylinder 22. It can be understood that the cone has a shape with a large upper opening and a small lower opening. As can be understood, the first flange and the second flange are respectively installed at the upper end and the lower end of the sleeve and are used for sealing the upper end and the lower end of the cylinder 22, so that the hydrogen-containing waste gas of the nuclear power plant entering the cylinder 22 is ensured not to leak.
In addition, the first flange may be designed to take out the activated carbon retention bed 21 from the upper port of the cylinder 22 for later maintenance; the design of the second flange provides an inlet for periodically detecting the adsorption performance of the activated carbon particles 214 in the future; before the activated carbon retention bed 21 is maintained, the second flange needs to be opened, and N is blown into the cylinder 22 through the lower port of the cylinder 222Thereby ensuring that the radioactivity content and the hydrogen content of the hydrogen-containing waste gas of the nuclear power plant which is retained in the cylinder 22 are reduced.
In one embodiment, as shown in fig. 6, the processing unit 2 further comprises a flow guide tube through which the inlet of the same body is connected to the layered carbon bed. As can be understood, the activated carbon particles 214 have a certain radioactivity after absorbing the exhaust gas discharged from the nuclear power plant; radioactive substances released by the activated carbon particles 214 pass through the outer wall of the barrel 22 and are released to the external environment of the nuclear electric control area; in order to reduce the influence of the activated carbon particles 214 on the external environment, the flow guide pipe presents a state that the middle flow rate of the hydrogen-containing waste gas of the nuclear power plant discharged to the first layered carbon bed 212 is large and the outer flow rate of the hydrogen-containing waste gas of the nuclear power plant is small (specifically, the cross section of the opening of the flow guide pipe gradually decreases from the partition plate 211 along the inner wall of the cylinder 22, that is, the opening of the flow guide pipe close to the partition plate 211 is large, and the opening of the flow guide pipe close to the inner wall of the cylinder 22 is small), and the design of the flow guide pipe increases the safety of.
In one embodiment, as shown in fig. 3 and 4, the processing unit 2 further includes a plurality of legs mounted on an outer wall of the cylinder 22 for supporting the cylinder 22. It can be understood that the number of the legs 7 can be designed according to actual requirements, for example, three legs are uniformly arranged along the circumferential direction of the cylinder 22, and for example, four legs are uniformly arranged along the circumferential direction of the cylinder 22.
In one embodiment, as shown in fig. 5 and 6, the first layered carbon bed 212 includes at least two first semicircular bearing plates 2121 arranged at intervals along the axial direction of the cylinder 22, and the second layered carbon bed 213 includes at least two second semicircular bearing plates 2131 arranged at intervals along the axial direction of the cylinder 22; each of the first semicircular bearing plate 2121 and each of the second semicircular bearing plate 2131 is mounted with the activated carbon particles 214. It can be understood that the first semicircular bearing plate 2121 and the second semicircular bearing plate 2131 can be arranged into five blocks, six blocks, eight blocks, ten blocks, etc. according to actual requirements; the partition 211 partitions an inner installation space of the cylinder 22 into a first space for installing the first semicircular bearing plate 2121 and a second space for installing the second bearing plate. Each of the first semicircular bearing plate 2121 and the second semicircular bearing plate 2131 is designed in a semicircular shape, so that the inner space of the cylinder 22 can be utilized to the maximum extent, more activated carbon particles 214 can be arranged, and the adsorption efficiency of the activated carbon retention bed 21 on the hydrogen-containing waste gas of the nuclear power station is improved.
Further, the distance between each first semicircular bearing plate 2121 can be set according to actual requirements, and the distance between each second semicircular bearing plate 2131 can be set according to actual requirements.
In one embodiment, the treatment unit 2 further comprises a spreader (not shown) for lifting the active retention bed from within the cylinder 22. It can be understood that the lifting appliance can be installed on a cross beam of a house, when the activated carbon retention bed 21 needs to be taken down from the cylinder 22, the lifting appliance can lift the activated carbon retention bed 21 from the cylinder 22, so that nuclear power plant maintenance personnel can take out the activated carbon retention bed 21 conveniently, and the workload of the nuclear power plant maintenance personnel is reduced.
In one embodiment, as shown in fig. 3, the cylinder 22 is further provided with an upstream gas sampling port 221 and a downstream gas sampling port (not shown), wherein the upstream gas sampling port 221 is arranged at the inlet position of the cylinder 22, and the downstream gas sampling port is arranged at the outlet position of the cylinder 22. It can understand, follow gaseous sample connection 221 of upper reaches can extract not the radioactive dose of the nuclear power station hydrogen-containing waste gas of active carbon detention bed 21 decay, follow gaseous sample connection of lower reaches can extract the process the radioactive dose of the nuclear power station hydrogen-containing waste gas of active carbon detention bed 21 decay can verify through comparison between the two the effect of detaining of active carbon detention bed 21 to nuclear power station maintainer can in time be right active carbon detention bed 21 overhauls, has avoided this nuclear power station hydrogen-containing waste gas treatment system to appear the nuclear power station hydrogen-containing waste gas accident that discharges not up to standard.
In one embodiment, as shown in fig. 2, the monitoring emission unit 3 further includes a gas filter and an emission control valve 34; the inlet of the gas filter is communicated with the outlet of the active carbon retention bed 21, the outlet of the gas filter is communicated with the inlet of the radioactivity detector, and the radioactivity detector is communicated with the inlet of the ventilation device through a quick discharge control valve 34. Specifically, the gas filter 33 may be installed in the exhaust duct between the outlet of the activated carbon retention bed 21 and the inlet of the ventilation device, and is used for passing the hydrogen-containing exhaust gas of the nuclear power plant into the radioactivity detector and the emission control valve 34, so that the cleanness of the hydrogen-containing exhaust gas of the nuclear power plant discharged from the ventilation device is ensured, and the service life of the radioactivity detector is prolonged. The emission control valve 34 can automatically discharge the hydrogen-containing waste gas of the nuclear power station output by the activated carbon retention bed 21, and the operation cost of the hydrogen-containing waste gas treatment system of the nuclear power station is reduced. In addition, the design of the gas filter 33 ensures the cleanliness of the hydrogen-containing waste gas of the nuclear power plant entering the ventilation device, and prolongs the service life of the emission control valve 34 and other downstream equipment.
In one embodiment, as shown in fig. 2, the hydrogen-containing off-gas treatment system of the nuclear power plant further comprises a return pipe 4, and the emission control valve 34 comprises a first outlet and a second outlet; a first outlet of the discharge control valve 34 communicates with an inlet of the ventilating device, and a second outlet of the discharge control valve 34 communicates with an inlet of the pressure regulating valve 11 through the return pipe 4. It is to be understood that the first outlet is a normally open outlet, and when the amount of radiation of the hydrogen-containing waste gas of the nuclear power plant after being treated by the pretreatment unit 1 and the single treatment end, which is detected by the radioactivity detector, reaches an emission standard, the emission control valve 34 controls the hydrogen-containing waste gas of the nuclear power plant, which is delivered from the treatment unit 2, to be directly discharged into the ventilation device. When the radioactivity detector detects that the radioactivity content of the hydrogen-containing waste gas of the nuclear power plant delivered from the treatment unit 2 does not reach the standard, the emission control valve 34 closes the first outlet and opens the second outlet, so that the hydrogen-containing waste gas of the nuclear power plant treated by the treatment unit 2 flows into the front end of the pretreatment unit 1 through the second outlet again, the hydrogen-containing waste gas of the nuclear power plant flowing back passes through the pretreatment unit 1 and the treatment unit 2 in sequence, and is emitted into the ventilation device through the first outlet after the radioactivity detector detects that the radioactivity content of the hydrogen-containing waste gas of the nuclear power plant reaches the standard. In the invention, the design of the discharge control valve 34 and the return pipe 4 further ensures the standard degree of the hydrogen-containing waste gas discharged by the nuclear power station after passing through the hydrogen-containing waste gas treatment system of the nuclear power station, and avoids the hydrogen-containing waste gas of the nuclear power station with substandard radioactivity from being discharged into the air.
In an embodiment, the monitoring discharge unit 3 further comprises an alarm device connected to the radioactivity detector. It can be understood that, when the radioactivity detector detects that the radioactivity content of the hydrogen-containing waste gas of the nuclear power plant processed by the pretreatment unit 1 and the processing unit 2 does not reach the standard, the radioactivity detector sends out an alarm signal to the alarm device, the alarm device sends out an alarm signal (voice broadcast, signal lamp display and the like), and meanwhile, the staff of the nuclear power plant timely detects and maintains each component in the hydrogen-containing waste gas processing system of the nuclear power plant.
The present invention is not limited to the above preferred embodiments, and any modifications, equivalent replacements, and improvements made within the spirit and principle of the present invention should be included in the protection scope of the present invention.
Claims (10)
1. A system for treating hydrogen-containing waste gas from a nuclear power plant, comprising:
the pretreatment unit comprises a pressure regulating valve for regulating the pressure of the hydrogen-containing waste gas of the nuclear power station and a silica gel dryer for dehumidifying the hydrogen-containing waste gas of the nuclear power station; the inlet of the pressure regulating valve is connected with the outlet of a compressor of a hydrogen-containing waste gas system of the nuclear power station, and the outlet of the pressure regulating valve is connected with the inlet of the silica gel dryer;
a treatment unit comprising a retentate bed of activated carbon; the inlet of the active carbon retention bed is connected with the outlet of the silica gel dryer;
the monitoring and discharging unit comprises a ventilation device communicated with the external environment and a radioactivity monitor installed on the ventilation device; the inlet of the ventilation device is connected with the outlet of the active carbon retention bed;
after the hydrogen-containing waste gas discharged by the exhaust system of the nuclear power station is subjected to pressure regulation and drying treatment by the pretreatment unit, the hydrogen-containing waste gas flows into the treatment unit and is retained and decayed by the activated carbon retention bed, and qualified waste gas monitored by the radioactivity monitor is discharged into the external environment by the monitoring discharge unit.
2. The system for treating the hydrogen-containing waste gas of the nuclear power plant as claimed in claim 1, wherein the pretreatment unit further comprises a pre-dryer for cooling and dehumidifying the hydrogen-containing waste gas of the nuclear power plant; and the inlet of the pressure regulating valve is connected with the outlet of a compressor of a hydrogen-containing waste gas system of the nuclear power station through the pre-dryer.
3. The system for treating hydrogen-containing waste gas from nuclear power plants according to claim 2, wherein the pre-dryer is provided with a condensate collecting pipe; the pretreatment unit also comprises a condensate collection tank communicated with the outlet of the condensate collection pipe.
4. The system for treating hydrogen-containing waste gas of a nuclear power plant according to claim 1, wherein the pretreatment unit further comprises a regeneration heater for regenerating the silica gel dryer.
5. The nuclear power plant hydrogen-containing exhaust gas treatment system according to claim 1, wherein the treatment unit includes a cylinder for mounting the retentate bed, the activated carbon retentate bed including a partition plate and first and second layered carbon beds connected on opposite sides of the partition plate; the first layered carbon bed and the second layered carbon bed are arranged along the axial direction of the cylinder and are filled with activated carbon particles; the inlet of the cylinder is connected with the outlet of the silica gel dryer, and the outlet of the cylinder is communicated with the ventilation device.
6. The nuclear power plant hydrogen-containing exhaust gas treatment system according to claim 5, wherein the first layered carbon bed includes at least two first semicircular bearing plates arranged at intervals in the axial direction of the barrel, and the second layered carbon bed includes at least two second semicircular bearing plates arranged at intervals in the axial direction of the barrel; and each first semicircular bearing plate and each second semicircular bearing plate are filled with the activated carbon particles.
7. The nuclear power plant hydrogen-containing exhaust gas treatment system according to claim 5, wherein the treatment unit further comprises a hoist for hoisting the active retention bed from within the cylinder.
8. The system for treating hydrogen-containing waste gas of a nuclear power plant according to claim 5, wherein the cylinder is further provided with an upstream gas sampling port and a downstream gas sampling port, the upstream gas sampling port is provided at an inlet position of the cylinder, and the downstream gas sampling port is provided at an outlet position of the cylinder.
9. The nuclear power plant hydrogen-containing exhaust gas treatment system according to claim 1, wherein the monitoring emission unit further includes a gas filter and an emission control valve; the inlet of the gas filter is communicated with the outlet of the activated carbon retention bed, the outlet of the gas filter is communicated with the inlet of the radioactivity detector, and the radioactivity detector is communicated with the inlet of the ventilation device through the discharge control valve.
10. The nuclear power plant hydrogen-containing off-gas treatment system according to claim 9, further comprising a return line, the emission control valve including a first outlet and a second outlet; the first outlet of the discharge control valve is communicated with the inlet of the ventilation device, and the second outlet of the discharge control valve is communicated with the inlet of the pressure regulating valve through the return pipe.
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| CN115608102A (en) * | 2022-01-27 | 2023-01-17 | 江苏希捷新能源工程技术有限公司 | Application method of waste gas treatment system of nuclear power station |
| CN116721790A (en) * | 2023-06-28 | 2023-09-08 | 中核环保产业有限公司 | Multistage treatment device for hydrogen-containing waste gas of nuclear power station and application method of multistage treatment device |
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| CN113963829A (en) * | 2021-10-27 | 2022-01-21 | 中国核动力研究设计院 | Method and system for treating radioactive waste gas of isotope production line |
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