CN215730900U - Radioactive waste gas treatment system for nuclear facility - Google Patents
Radioactive waste gas treatment system for nuclear facility Download PDFInfo
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- CN215730900U CN215730900U CN202121244795.2U CN202121244795U CN215730900U CN 215730900 U CN215730900 U CN 215730900U CN 202121244795 U CN202121244795 U CN 202121244795U CN 215730900 U CN215730900 U CN 215730900U
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Abstract
The utility model discloses a radioactive waste gas treatment system for nuclear facilities, which comprises: a buffer device for receiving and mixing the radioactive waste gas; the compression device is connected with the buffer device and is used for boosting and cooling the radioactive waste gas; the delayed decay device is connected with the compression device and is used for delaying decay of the radioactive waste gas and removing water vapor, organic impurities, radioactive aerosol and fission nuclides in the radioactive waste gas; and the discharge pressure reducing device is connected with the delayed decay device and is used for reducing the pressure of the radioactive waste gas. This radioactive waste gas treatment system for nuclear facilities has greatly improved the purifying effect to radioactive waste gas, has reduced equipment size and space and has taken up an area of, has reduced secondary waste production volume, has realized preventing that the system from taking place the radioactivity and to the risk of environmental leakage, hydrogen explosion and conflagration, has greatly guaranteed the security and the reliable operation of system, in the radioactive waste gas treatment field of nuclear facilities, has stronger extensive application.
Description
Technical Field
The utility model belongs to the technical field of nuclear facilities, and particularly relates to a radioactive waste gas treatment system for a nuclear facility.
Background
The radioactive waste gas generated during the normal operation and overhaul of the nuclear facility mainly comes from reactor coolant and nitrogen purging waste gas, the main components of the radioactive waste gas are nitrogen, hydrogen, fission gas such as radioactive nuclide krypton, xenon, radioactive aerosol and the like, the fluctuation of the characteristics of the waste gas source is large, and the exhaust pressure, the exhaust flow and the exhaust time are different greatly. The radioactive waste gas is treated by compressed storage decay and active carbon retention decay.
The compression storage decay method is characterized in that waste gas is pressurized and then sent to a decay tank to be stored for at least 40d under high pressure, and the method has the problems of large capacity of the decay tank, large floor area, large leakage risk and overpressure risk during tank dumping and the like.
Active carbon is used for detention and decay, and the active carbon is widely used for dynamically adsorbing and delaying cracked gases of krypton and xenon under the environment of normal temperature and normal pressure or micro-negative pressure, so that the aim of reducing the radioactivity level of the waste gas is fulfilled. Because rate of admitting air, humidity, temperature, pressure all can influence the adsorption effect of active carbon to the radionuclide, consequently to the great waste gas of characteristic fluctuation and the great nuclear facility of waste gas production volume, if adopt the method that the active carbon stays the decay under normal atmospheric temperature and pressure, will lead to the adsorption effect poor, thereby the active carbon dress volume is too big secondary waste production volume is big, economic nature relatively poor scheduling problem.
SUMMERY OF THE UTILITY MODEL
The technical problem to be solved by the utility model is to provide a radioactive waste gas treatment system for a nuclear facility, aiming at the defects in the prior art, and effectively solving the problems in the prior art that the occupied area of equipment is large, the risk of inverted groove leakage is large, the influence of the air inlet characteristic fluctuation of radioactive waste gas on the retention effect is large, the loading amount of activated carbon is large due to normal pressure adsorption, the secondary waste amount is large, the economical efficiency is poor, and the like.
The technical scheme adopted for solving the technical problem of the utility model is to provide a radioactive waste gas treatment system for nuclear facilities, which comprises:
a buffer device for receiving and mixing the radioactive waste gas;
the compression device is connected with the buffer device and is used for boosting and cooling the radioactive waste gas;
the delayed decay device is connected with the compression device and is used for delaying decay of the radioactive waste gas and removing water vapor, organic impurities, radioactive aerosol and fission nuclides in the radioactive waste gas;
and the discharge pressure reducing device is connected with the delayed decay device and is used for reducing the pressure of the radioactive waste gas.
Preferably, the radioactive waste gas treatment system for nuclear facilities further includes:
a flame retardant device comprising: the flame retardant device comprises a first flame retardant device arranged at the inlet of the delayed decay device and a second flame retardant device arranged at the outlet of the delayed decay device, wherein the flame retardant device is used for retarding flame.
Preferably, the radioactive waste gas treatment system for nuclear facilities further includes:
the dehumidifying device is arranged between the compressing device and the delayed decay device, is respectively connected with the compressing device and the delayed decay device, and is used for removing condensed water of compressed waste gas discharged from the compressing device and reducing absolute humidity in the compressed waste gas.
Preferably, the dehumidifying apparatus includes: the system comprises a steam-water separator, a liquid level instrument, a pressure instrument, a gas outlet valve, a humidity monitoring instrument, a dehumidification bed, a bypass valve, an air inlet valve, an air outlet valve, a drain valve and a drain valve; the liquid level meter is connected with the steam-water separator, and the pressure meter is connected with the steam-water separator; the dehumidification bed is connected with catch water, the dehumidification bed still is connected with the decay device that delays, the dehumidification bed is arranged in reducing the absolute humidity among the compressed exhaust gas, be provided with the gas outlet valve on the connecting tube between dehumidification bed and catch water, humidity monitor, be provided with the drain valve on the drain pipe of catch water exit linkage, be provided with the drain valve on the drain pipe of dehumidification bed exit linkage, be provided with the bypass valve on the bypass pipeline of being connected between dehumidification bed and the decay device that delays, be provided with the admission valve on the connecting tube of dehumidification bed import, be provided with the air outlet valve on the connecting tube between dehumidification bed and the decay device that delays.
Preferably, the radioactive waste gas treatment system for nuclear facilities further includes:
on-line sample cabinet, with buffer entrance connection, on-line sample cabinet is used for the radioactive waste gas sample of buffer entry and to hydrogen concentration, oxygen concentration carries out continuous monitoring, on-line sample cabinet still with delay decay device entry, delay decay device exit linkage, on-line sample cabinet still is used for the radioactive waste gas sample of delay decay device entry, delay decay device export and to hydrogen concentration, oxygen concentration and radioactive concentration carry out manual sampling monitoring.
Preferably, the radioactive waste gas treatment system for nuclear facilities further includes:
and the nitrogen fire extinguishing device is connected with the inlet of the delayed decay device and is used for extinguishing fire.
Preferably, the nitrogen fire extinguishing apparatus includes: the nitrogen source, the manometer admits air, the decompression governing valve, nitrogen gas supply valve, the relief valve, the nitrogen source and delayed decay device entry linkage, be provided with the manometer admits air on the connecting tube between nitrogen source and the delayed decay device entry, nitrogen gas supply valve, the manometer of admitting air is close to the export of nitrogen source and is used for detecting the pressure of nitrogen source, be connected with the lateral conduit on the connecting tube between nitrogen source and delayed decay device entry and discharge pressure relief device's outlet pipe connection, be provided with the decompression governing valve on this lateral conduit, be provided with the lateral conduit on the pipeline between nitrogen gas supply valve and nitrogen source, be provided with the relief valve on this lateral conduit, this lateral conduit is used for connecting the chimney.
Preferably, the buffer device includes: the device comprises an air inlet valve, a buffer storage tank, a nitrogen source, a nitrogen gas supply valve, a safety valve, a chimney and a drain valve, wherein the buffer storage tank is connected with an air inlet pipeline and is connected with a radioactive waste gas inlet through an air inlet pipeline, the air inlet pipeline is provided with the air inlet valve, the air inlet pipeline is provided with a branch pipeline, the branch pipeline is connected with the nitrogen source, the branch pipeline is provided with the nitrogen gas supply valve, the air inlet pipeline is provided with an overpressure release pipeline, the overpressure release pipeline is connected with the chimney, the safety valve is arranged on the overpressure release pipeline, and the drain valve is arranged on a drain pipeline connected with an outlet of the buffer storage tank.
Preferably, the compressing device includes: the first compression device and the second compression device are connected in parallel, the first compression device and the second compression device are respectively connected with the buffer device and the delayed decay device, and the first compression device and the second compression device are used for one by one. And a check valve is arranged on a main pipe of the buffer storage tank which is respectively connected with the first compression device and the second compression device which are connected in parallel.
Preferably, the first compressing device includes: the device comprises an air inlet valve, a pressure gauge, a filter, an exhaust gas compressor, a compressed exhaust gas cooler, a thermometer, a pressure gauge and a compressed gas discharge valve which are sequentially connected, wherein the air inlet valve is connected with a buffer device, and the compressed gas discharge valve is connected with a delayed decay device;
the second compressing device includes: the device comprises an air inlet valve, a pressure gauge, a filter, a waste gas compressor, a compressed waste gas cooler, a thermometer, a pressure gauge and a compressed gas discharge valve which are sequentially connected, wherein the air inlet valve is connected with a buffer device, and the compressed gas discharge valve is connected with a delayed decay device.
Preferably, the delayed decay apparatus comprises: the device comprises a pretreatment bed, a delay bed, a bypass valve, an air inlet valve, an air outlet valve, a drain valve and a drain valve, wherein the delay bed is connected with the pretreatment bed, the delay bed is connected with the delay bed, the inlet pipeline of the pretreatment bed is provided with the air inlet valve, the inlet pipeline of the delay bed is provided with the air inlet valve, the connecting pipeline between the pretreatment bed and the delay bed is provided with the air outlet valve, the connecting pipeline between the delay bed and the delay bed is provided with the air outlet valve, the drain pipeline connected with the outlet of the pretreatment bed is provided with the drain valve, the drain pipeline connected with the outlet of the delay bed is provided with the drain valve, a bypass valve is provided in a bypass line connecting the pretreatment bed and the delay bed, a bypass valve is provided in a bypass line connecting the delay bed and the delay bed, and a bypass valve is provided in a bypass line connecting the delay bed and the discharge pressure reducing device.
Preferably, the pretreatment bed, the delay bed and the filling medium in the delay bed are spherical coconut shell activated carbon.
The utility model solves the influence of the fluctuation of the air inlet characteristics (pressure, flow and the like) of the radioactive waste gas through the buffer device, and improves the steady-state operation of the compression device and the delayed decay device; the compression device is self-protected, so that the damage of the compression device and the risk of overpressure hydrogen leakage of the system are prevented; the cooling and dehumidifying device which can be automatically or manually switched protects and prolongs the service life of the delayed decay device; through nitrogen gas extinguishing device and fire-retardant device, realized that the system puts out a fire fast and prevents that the conflagration from spreading.
The radioactive waste gas treatment system for the nuclear facility greatly improves the purification effect of radioactive waste gas, greatly reduces the size and the space occupation of equipment, reduces the generation amount of secondary waste (waste medium, waste water and the like), greatly prevents the system from radioactive leakage to the environment, hydrogen explosion and fire risks, greatly ensures the safety and the reliable operation of the system, and has stronger wide applicability in the field of radioactive waste gas treatment of the nuclear facility.
Drawings
Fig. 1 is a schematic configuration diagram of a radioactive exhaust gas treatment system for nuclear facilities in embodiment 2 of the present invention.
In the figure: 1-buffer storage tank, 2, 3-waste gas compressor, 4, 5 compressed waste gas cooler, 6-steam-water separator, 7-dehumidification bed, 8-pretreatment bed, 9, 10-delay bed, 11-online sampling cabinet, 12-first flame retardant, 13-second flame retardant, 14-discharge pressure reducing device, 15-radioactive waste gas inlet, 16-ventilation filter set, 17, 18, 19-nitrogen source, 20-chimney, 21, 22-hydrophobic, 23, 24, 25, 26-cold source, 27, 28, 29, 32, 33, 34, 40, 41-pressure gauge, 30, 31, 37, 38, 39-thermometer, 35-liquid level gauge, 36-humidity gauge, 42-radioactivity monitoring gauge, 43, 44-oxygen concentration monitoring gauge, 45-hydrogen concentration monitoring gauge, 48. 57, 61-safety valve, 46, 52, 53, 64, 67, 70, 73-inlet valve, 47, 60-nitrogen gas supply valve, 49, 78, 79, 80, 81-sampling valve, 50, 63-sampling return valve, 62-nitrogen purge valve, 65, 68, 71, 75-bypass valve, 66, 69, 72, 74-outlet valve, 51-check valve, 54, 55-compressed gas discharge valve, 56-compressor pressure reduction valve, 58-gas outlet valve, 86, 59, 82, 83, 84, 85, 87-trap, 77-system discharge valve, 76-pressure reduction valve, 88, 89, 90-nitrogen isolation valve, 91, 92-filter, 93, 94-branch line, 95-inlet line, 96-branch line, 97-overpressure discharge line, 98-trap, 99. 100, 101, 105, 109, 110, 111, 119, 120, 121, 122, 123, 124, 125, 126, 127, 128, 129, 130, 131, 133-connecting pipes, 102, 103, 104, 108-bypass pipes, 106, 107, 116, 117, 118-hydrophobic pipes, 112-outlet pipes, 113, 114, 115-inlet pipes, 132-mother pipes.
Detailed Description
In order to make the technical solutions of the present invention better understood, the present invention will be described in further detail with reference to the accompanying drawings and specific embodiments.
Reference will now be made in detail to embodiments of the present patent, examples of which are illustrated in the accompanying drawings, wherein like or similar reference numerals refer to the same or similar elements or elements having the same or similar function throughout. The embodiments described below with reference to the drawings are exemplary only for the purpose of explaining the present patent and are not to be construed as limiting the present patent.
Example 1
The present embodiment provides a radioactive waste gas treatment system for nuclear facilities, including:
a buffer device for receiving and mixing the radioactive waste gas;
the compression device is connected with the buffer device and is used for boosting and cooling the radioactive waste gas;
the delayed decay device is connected with the compression device and is used for delaying decay of the radioactive waste gas and removing water vapor, organic impurities, radioactive aerosol and fission nuclides in the radioactive waste gas;
and the discharge pressure reducing device is connected with the delayed decay device and is used for reducing the pressure of the radioactive waste gas.
The radioactive waste gas treatment system for the nuclear facility in the embodiment greatly improves the purification effect of radioactive waste gas, greatly reduces the size of equipment and the occupied space, reduces the production amount of secondary waste (waste medium, waste water and the like), greatly prevents the system from generating radioactive leakage to the environment, hydrogen explosion and fire risks, greatly ensures the safety and reliable operation of the system, and has strong wide applicability in the field of radioactive waste gas treatment of the nuclear facility.
Example 2
As shown in fig. 1, the present embodiment provides a radioactive exhaust gas treatment system for nuclear facilities, including:
a buffer device for receiving and mixing the radioactive waste gas;
the compression device is connected with the buffer device and is used for boosting and cooling the radioactive waste gas, so that the adsorption effect of the delayed decay device on the radioactive waste gas is improved;
the delayed decay device is connected with the compression device and is used for delaying decay of the radioactive waste gas and removing water vapor, organic impurities, radioactive aerosol and fission nuclides in the radioactive waste gas;
and a discharge pressure reducing device 14 connected with the delayed decay device and used for reducing the pressure of the radioactive waste gas.
Preferably, the radioactive waste gas treatment system for nuclear facilities further includes:
a flame retardant device comprising: a first flame retardant device 12 arranged at the inlet of the delayed decay device and a second flame retardant device 13 arranged at the outlet of the delayed decay device, wherein the flame retardant device is used for retarding flame and preventing the fire from spreading.
Preferably, the radioactive waste gas treatment system for nuclear facilities further includes:
the dehydrating unit sets up between compression device and delay decay device, and the dehydrating unit is connected with compression device, delay decay device respectively, and the dehydrating unit is arranged in getting rid of the comdenstion water from compression device exhaust compression waste gas, reduces the absolute humidity in the compression waste gas to improve and guarantee the higher adsorption effect of delay decay device.
Preferably, the dehumidifying apparatus includes: the system comprises a steam-water separator 6, a liquid level meter 35, a pressure meter 34, a gas outlet valve 58, a humidity monitoring meter 36, a dehumidification bed 7, a bypass valve 65, an air inlet valve 64, an air outlet valve 66, a drain valve 59 and a drain valve 82; the steam-water separator 6 is connected with the compression device, the steam-water separator 6 is used for removing condensed water of compressed waste gas discharged from the compression device, the liquid level meter 35 is connected with the steam-water separator 6, and the pressure meter 34 is connected with the steam-water separator 6; the dehumidification bed 7 is connected with the steam-water separator 6, the dehumidification bed 7 is also connected with the delayed decay device, the dehumidification bed 7 is used for reducing absolute humidity in the compressed waste gas, a gas outlet valve 58 and a humidity monitoring instrument 36 are arranged on a connecting pipeline 105 between the dehumidification bed 7 and an outlet of the steam-water separator 6, a drain valve 59 is arranged on a drain pipeline 106 connected with an outlet of the steam-water separator 6, a drain valve 82 is arranged on a drain pipeline 107 connected with an outlet of the dehumidification bed 7, a bypass valve 65 is arranged on a bypass pipeline 108 connected between the dehumidification bed 7 and the delayed decay device, an air inlet valve 64 is arranged on a connecting pipeline 109 at the inlet of the dehumidification bed 7, and an air outlet valve 66 is arranged on a connecting pipeline 110 between the dehumidification bed 7 and the delayed decay device. A nitrogen isolation valve 90 is arranged on a connecting pipeline 133 between the outlet of the steam-water separator 6 and the chimney 20.
In this embodiment, the desiccant bed 7 is connected to the outlet of the steam-water separator 6 through the connecting pipe 105, and if the humidity monitoring instrument 36 reaches a preset humidity value, the desiccant bed 7 is put into operation, that is, the interlock air inlet valve 64 and the air outlet valve 66 are opened, and the bypass valve 65 is closed. Thereby further reducing the humidity of the compressed waste gas and ensuring that the delayed decay device has higher adsorption retention effect on radioactive nuclide krypton, xenon and the like. The monitoring and alarming of the humidity monitoring instrument 36 can effectively reduce the amount of secondary waste increased due to unnecessary dehumidification.
The liquid level meter 35 and the pressure meter 34 are used for interlocking the opening and closing of the drain valve 59 and the gas outlet valve 58 and interlocking the starting and stopping of the exhaust gas compressor 2 and the exhaust gas compressor 3 so as to prevent moisture from entering a downstream pipeline or equipment. The pressure gauge 34 is used for indicating the gas phase pressure of the compressed waste gas after condensation and dehumidification, and the liquid level gauge 35 is provided with a liquid level alarm.
When the liquid level detected by the liquid level meter 35 is higher than a first preset liquid level of the steam-water separator 6 and the pressure detected by the pressure meter 34 is higher than a first preset pressure of the steam-water separator 6, the waste gas compressor 2 and the waste gas compressor 3 are interlocked and all shut down; when the liquid level detected by the liquid level meter 35 is higher than the second preset liquid level of the steam-water separator 6, and the pressure detected by the pressure meter 34 is higher than the second preset pressure of the steam-water separator 6, the interlocking drain valve 59 is automatically opened to drain water. The first preset liquid level of the steam-water separator 6 is higher than the second preset liquid level of the steam-water separator 6, and the first preset pressure of the steam-water separator 6 is higher than the second preset pressure of the water separator 6. When the liquid level detected by the liquid level meter 35 is lower than the second preset liquid level of the steam-water separator 6, and the pressure detected by the pressure meter 34 is lower than the second preset pressure of the steam-water separator 6, the interlocking drain valve 59 is automatically closed, so that the radioactive gas is prevented from diffusing downstream.
The dehumidifying bed 7 is a container filled with a medium, and is used for filling the dehumidifying medium, wherein the dehumidifying medium comprises one or more of gel, resin, zeolite and activated carbon. The dehumidification bed 7 can be selectively put into operation or bypassed for standby according to the humidity monitoring instrument 36. Alternatively, the desiccant bed 7 is a chiller.
In this embodiment, the steam-water separator 6 is any one of a coil pipe, a sleeve pipe, or an expansion pipe, and is used for separating and removing condensed water after cooling the compressed exhaust gas.
Preferably, the radioactive waste gas treatment system for nuclear facilities further includes:
on-line sampling cabinet 11, with buffer entrance connection, on-line sampling cabinet 11 is used for the radioactive waste gas sample of buffer entrance and to hydrogen concentration, oxygen concentration carries out continuous monitoring, on-line sampling cabinet 11 still with delay decay device entry, delay decay device exit linkage, on-line sampling cabinet 11 still is used for the radioactive waste gas sample of delay decay device entry, the export of delay decay device and carries out continuous monitoring to hydrogen concentration, oxygen concentration.
And a first oxygen monitoring instrument 43, a second oxygen monitoring instrument 44 and a hydrogen monitoring instrument 45 are arranged in the online sampling cabinet. The online sampling cabinet discharges the drainage 21 through the connecting pipeline 131 and the connecting pipeline 131, and the connecting pipeline 131 is provided with a drainage valve 87
The online sampling cabinet 11 is connected with the online air inlet pipeline 95 through a connecting pipeline 123, the online sampling cabinet 11 is further connected with the online air inlet pipeline 95 through a connecting pipeline 124, a sampling valve 49 is arranged on the connecting pipeline 123, and a sampling return valve 50 is arranged on the connecting pipeline 124.
The online sampling cabinet 11 is connected with the inlet of the pretreatment bed 8 through a connecting pipeline 125, and a sampling valve 78 is arranged on the connecting pipeline 125; the online sampling cabinet 11 is connected with the inlet of the delay bed 9 through a connecting pipeline 126, and a sampling valve 79 is arranged on the connecting pipeline 126; the online sampling cabinet 11 is connected with the inlet of the delay bed 10 through a connecting pipeline 127, and a sampling valve 80 is arranged on the connecting pipeline 127; the online sampling cabinet 11 is connected with the outlet of the delay bed 10 through a connecting pipe 128, and the connecting pipe 128 is provided with a sampling valve 81. The online sampling cabinet 11 is connected with the inlet of the dehumidification bed 7 through a connecting pipeline 129, and a sampling return valve 63 is arranged on the connecting pipeline 129. The online sampling cabinet 11 is connected with the nitrogen source 19 through a connecting pipeline 130, and the connecting pipeline 130 is provided with a nitrogen purge valve 62. Two sampling pumps, one for use and one for standby, and related pressure reducing valves, regulating valves and isolating valves are arranged in the online sampling cabinet 11.
The sampling valves related to the online sampling cabinet 11 are all electromagnetic valves, once the online sampling cabinet 11 leaks to cause high hydrogen concentration alarm at the top of the sampling cabinet or high oxygen concentration alarm in online monitoring, all the electromagnetic valves are interlocked to be automatically powered off and isolated, the nitrogen purging valve 62 is automatically opened for purging, the sampling return valve 63 is opened, and nitrogen purging is performed on the online sampling cabinet 11 so as to be convenient for maintenance. Specifically, the oxygen concentration is monitored by the first oxygen monitor 43 and the second oxygen monitor 43.
The online sampling cabinet 11 continuously monitors the oxygen concentration and the hydrogen concentration of the radioactive waste gas entering the buffer device on line so as to ensure that the system operates in an environment with the oxygen volume concentration lower than 2.4 percent, thereby avoiding the hydrogen explosion risk of the system.
The online sampling cabinet 11 is used for continuously monitoring the hydrogen concentration and the oxygen concentration in the waste gas entering the buffer storage tank 1 during the normal operation of the system, and ensuring that the system safely operates in the environment with the oxygen volume concentration lower than 2.4% through alarming and interlocking actions. In addition, the online sampling cabinet 11 is used for monitoring the nitrogen annihilation effect during the commissioning of the nitrogen fire extinguishing apparatus.
When the online sampling cabinet monitors that the oxygen concentration is higher than the first preset oxygen concentration, the interlocking main control room gives an alarm to remind an operator to perform related inspection. When the online sampling cabinet detects that the oxygen concentration is higher than the second preset oxygen concentration, the interlocking air inlet valve 46 is closed, and the nitrogen supply valve 47 is opened for nitrogen purging, so that the system is ensured to run safely in an environment with the oxygen volume concentration lower than 2.4%. The nitrogen annihilation effect is monitored by an oxygen concentration monitoring instrument of the online sampling cabinet, and once the oxygen concentration is low, the nitrogen extinguishment is sufficient.
In this embodiment, the online sampling cabinet 11 is provided with a manual sampling interface, and when the radioactivity monitoring meter 42 of the system discharge pipeline sends out a radioactivity level alarm, the waste gas at the outlet of each bed of the delayed decay device is manually sampled and analyzed to judge that the bed body is invalid. In addition, when the online sampling cabinet 11 fails, the waste gas in the corresponding pipeline of the system can be periodically sampled through the manual sampling interface, and the hydrogen concentration, the oxygen concentration and the radioactive concentration of the waste gas are subjected to inspection analysis.
Preferably, the radioactive waste gas treatment system for nuclear facilities further includes:
and the nitrogen fire extinguishing device is connected with the inlet of the delayed decay device and is used for extinguishing fire.
Preferably, the nitrogen fire extinguishing apparatus includes: the device comprises a nitrogen source 19, an inlet pressure gauge 40, a decompression regulating valve 76, a nitrogen gas supply valve 60 and a safety valve 61, wherein the nitrogen source 19 is connected with an inlet of the delayed decay device, the inlet pressure gauge 40 and the nitrogen gas supply valve 60 are arranged on a connecting pipeline 111 between the nitrogen source 19 and the inlet of the delayed decay device, an outlet of the inlet pressure gauge 40 close to the nitrogen source 19 is used for detecting the pressure of the nitrogen source, a branch pipeline 93 is connected to the connecting pipeline 111 between the nitrogen source 19 and the inlet of the delayed decay device and is connected with an outlet pipeline 112 of a discharge decompression device, the decompression regulating valve 76 is arranged on the branch pipeline 93, a branch pipeline 94 is arranged on a pipeline between the nitrogen gas supply valve 60 and the nitrogen source 19, the safety valve 61 is arranged on the branch pipeline 94, and the branch pipeline 94 is used for connecting a chimney 20.
The discharge pressure reducing device comprises two sets of pressure reducing mechanisms connected in parallel, wherein each set of pressure reducing mechanism is provided with a pressure reducing valve, an inlet and outlet isolating valve and a related pressure gauge. The exhaust gas purified by the delayed decay apparatus is decompressed and discharged to the ventilation filter apparatus 16, thereby preventing the ventilation filter apparatus 16 from being damaged by high pressure.
In this embodiment, the pressure relief valve 76 is used to maintain a slight positive pressure in the system during periods of system shutdown, thereby preventing oxygen from penetrating into the system to form an explosive oxyhydrogen mixture.
The discharge pressure reducing device is connected with the ventilation filter unit 16, a system discharge valve 77 is arranged on an outlet pipeline 112 of the discharge pressure reducing device, the system discharge valve 77 is interlocked with the radioactivity monitoring instrument 42, and the system discharge valve 77 is interlocked and opened after the radioactivity monitoring instrument 42 monitors that the radioactivity is qualified, and the system discharge valve is sent to the ventilation filter unit 16 to be purified and then discharged to the environment.
The opening and closing of the system drain valve 77 is interlockingly controlled by the pressure gauge 41 at the outlet of the drain relief device 14, the radioactivity monitoring gauge 42 on the system drain line, and the operating state of the vent filter bank 16. Thereby preventing the radioactive exhaust gas from being released to the environment beyond the standard and avoiding overpressure or adverse effects on the ventilation filter unit 16.
The system drain valve 77 is only allowed to open when the vent filter bank 16 is available and the radioactivity level monitored by the radioactivity monitoring meter 42 is acceptable. When the system exhaust valve 77 is opened and the pressure value monitored by the pressure gauge 41 is lower than the first preset pressure value of the system exhaust line, the interlock system exhaust valve 77 is automatically closed. When the system exhaust valve 77 is in a closed state and the pressure value monitored by the pressure gauge 41 is higher than a second preset pressure value of the system exhaust line, the interlock system exhaust valve 77 is automatically opened.
When the temperature is detected by the temperature meter at the top of the equipment room of the delayed decay device or any one of the temperature meters 37, 38 and 39 on the outlet pipelines of the pretreatment bed 8, the delay bed 9 and the delay bed 10, the interlocking nitrogen fire extinguishing system is put into operation, namely the nitrogen gas supply valve 60 is opened, the parallel locking exhaust gas compressor 2, the exhaust gas compressor 3 is stopped, and the gas outlet valve 58 and the system discharge valve 77 are automatically closed.
Preferably, the buffer device includes: the device comprises an air inlet valve 46, a buffer storage tank 1, a nitrogen source 17, a nitrogen gas supply valve 47, a safety valve 48, a chimney 20 and a drain valve 86, wherein the buffer storage tank 1 is connected with an air inlet pipeline 95 and is connected with a radioactive waste gas inlet 15 through an air inlet pipeline 95, the air inlet pipeline 95 is provided with the air inlet valve 46, the air inlet pipeline 95 is provided with a branch pipeline 96, the branch pipeline 96 is connected with the nitrogen source 17, the branch pipeline 96 is provided with the nitrogen gas supply valve 47, the air inlet pipeline 95 is provided with an overpressure discharge pipeline 97, the overpressure discharge pipeline 97 is connected with the chimney 20, the safety valve 48 is arranged on the overpressure discharge pipeline 97, the drain pipeline 98 connected with the outlet of the buffer storage tank 1 is provided with the drain valve 86, and drain 22 is discharged through the drain pipeline 98. The buffer tank 1 is connected with a drain member including, but not limited to, a drain valve 86. And the buffer device is used for receiving and mixing the radioactive waste gas from different pressures and exhaust flow rates collected by the radioactive waste gas inlet 15 so as to provide a stable air inlet state for a compression device connected with the buffer device.
And a pressure gauge 27 is arranged at the top of the buffer storage tank 1 and is used for displaying and sending alarm signals to a control room, and the nitrogen gas supply valve 47 is controlled to be opened and closed and the waste gas compressor 2 and the waste gas compressor 3 are controlled to be put into operation and stopped in an interlocking manner. The safety valve 48 is configured to prevent overpressure leakage of the buffer tank 1 caused by failure and shutdown of the compression device, and when the pressure of the buffer tank 1 reaches the trip setting value of the safety valve 48, the radioactive waste gas is discharged to the chimney 20 through the safety valve 48 via the overpressure discharge pipe 97. When the pressure value detected by the pressure gauge 27 is lower than the pressure value of the first preset buffer storage tank, all the waste gas compressors are controlled to stop running in an interlocking manner; when the pressure value detected by the pressure gauge 27 is lower than the second preset pressure value of the buffer storage tank, the nitrogen gas supply valve 47 is opened under the interlocking control, nitrogen gas is supplemented to the buffer storage tank 1 until the pressure setting requirement is met, and the nitrogen gas supply valve 47 is automatically closed to prevent the buffer storage tank 1 from excessively low pressure caused by the leakage of a buffer device and other reasons. Wherein, the pressure value of the second preset buffer storage tank is lower than that of the first preset buffer storage tank. When the pressure value detected by the pressure gauge 27 is higher than the pressure value of the third preset buffer storage tank, one of the waste gas compressors is controlled to be started automatically in an interlocking manner; when the pressure value detected by the pressure gauge 27 is higher than the pressure value of the fourth preset buffer storage tank, another exhaust gas compressor is controlled to start in an interlocking manner, and the pressure value of the fourth preset buffer storage tank is higher than the pressure value of the third preset buffer storage tank.
Preferably, the compressing device includes: the first compression device and the second compression device are connected in parallel, the first compression device and the second compression device are respectively connected with the buffer device and the delayed decay device, and the first compression device and the second compression device are used for one by one. When any one of the first compression device or the second compression device fails, the other compression device is automatically or manually put into operation, so that radioactive waste gas is guaranteed to enter the delayed decay device in a continuous stable state, the system is prevented from being stopped due to the failure of the waste gas compressor 2 and the waste gas compressor 3, and the continuous operation of the system can be realized.
Preferably, the first compressing device includes: the device comprises an air inlet valve 52, a pressure gauge 28, a filter 91, an exhaust gas compressor 2, a compressed exhaust gas cooler 4, a thermometer 30, a pressure gauge 32 and a compressed gas discharge valve 54 which are connected in sequence, wherein the air inlet valve 52 is connected with a buffer device, and the compressed gas discharge valve 54 is connected with a delayed decay device; the compressed exhaust gas cooler 4 is connected to a cold source 23 and a cold source 24, respectively.
The second compressing device includes: the device comprises an air inlet valve 53, a pressure gauge 29, a filter 92, an exhaust gas compressor 3, a compressed exhaust gas cooler 5, a thermometer 31, a pressure gauge 33 and a compressed gas discharge valve 55 which are sequentially connected, wherein the air inlet valve 53 is connected with a buffer device, and the compressed gas discharge valve 55 is connected with a delayed decay device. The compressed exhaust gas cooler 5 is connected to a cold source 25 and a cold source 26, respectively.
In this embodiment, the outlet pipelines of the compressed gas cooler 4 and the compressed gas cooler 5 are provided with a temperature meter 30, a temperature meter 31, a pressure meter 32 and a pressure meter 33 for monitoring the pressure rise and cooling effect of the waste gas and preventing the system from running in overpressure. The temperature meter 30 and the temperature meter 31 are used for monitoring the temperature of the compressed gas, when the temperature value is higher than the preset temperature value of the compressed gas, an alarm signal is sent to the control room, the exhaust gas compressor of the corresponding pipeline is controlled to stop running in an interlocking mode, and the temperature value is used for ensuring that the humidity of the exhaust gas meets the air inlet requirement of the delayed decay device; and a pressure gauge 32 and a pressure gauge 33 for monitoring the pressure of the compressed gas, and when the pressure value is higher than the preset pressure value of the compressed gas, sending an alarm signal to the control chamber to interlockingly control the waste gas compressor 2 and the waste gas compressor 3 of the corresponding pipeline to stop running. The exhaust gas compressor 2 and the exhaust gas compressor 3 are diaphragm compressors or liquid ring compressors in view of their better sealing performance. The filter 91 and the filter 92 are used for removing impurities in the exhaust gas or in the entrained pipeline, so as to protect and ensure the normal operation of the exhaust gas compressor 2 and the exhaust gas compressor 3.
In this embodiment, the start and stop of the waste gas compressor 2 and the waste gas compressor 3 are interlocked and controlled by the alarm signals of the pressure gauge 27, the pressure gauge 32, the pressure gauge 33, the temperature gauge 30, the pressure gauge 31, the steam-water separator liquid level 35, the temperature gauge 37, the temperature gauge 38 and the temperature gauge 39 on the top of the buffer storage tank 1.
In this embodiment, the waste gas after waste gas compressor 2, the 3 pressurizations of waste gas compressor gets into compressed gas cooler 4, compressed gas cooler 5, carries out circulative cooling through cold source 23, cold source 24, cold source 25, cold source 26, cold source 23, cold source 24, cold source 25, cold source 26 medium can be to establish cold water, also can be the refrigerated water, and then realizes compressed waste gas cooling and condensation.
In this embodiment, before and after the start and stop of exhaust gas compressor 2, exhaust gas compressor 3, all release pressure to buffer storage tank 1 through the pipeline of connecting relief pressure valve 56, and then protection exhaust gas compressor 2, exhaust gas compressor 3 can normal operating. Relief valve 57 is provided in the parallel line of pressure relief valve 56 to prevent leakage of excess pressure at the outlet of the compression device.
A connecting pipeline 119 between the intake valve 52 and the filter 91 is connected with a connecting pipeline 120 between the intake valve 53 and the filter 92 through a connecting pipeline 121, an isolation valve 88 and an isolation valve 89 are arranged on the connecting pipeline 121, the isolation valve 88 is close to the connecting pipeline 119, the isolation valve 89 is close to the connecting pipeline 120, and a branch pipeline is arranged on the connecting pipeline between the isolation valve 88 and the isolation valve 89 to be connected with the nitrogen source 18. A pressure reducing valve 56 is arranged on a connecting pipeline 122 between the buffer storage tank 1 and the steam-water separator 6, and a safety valve 57 is arranged on a parallel pipeline of the pressure reducing valve 56 so as to prevent overpressure leakage at an outlet of the compression device.
Preferably, the delayed decay apparatus comprises: the pretreatment bed 8, the delay bed 9, the delay bed 10, the bypass valve 68, the bypass valve 71, the bypass valve 75, the air inlet valve 67, the air inlet valve 70, the air inlet valve 73, the air outlet valve 69, the air outlet valve 72, the air outlet valve 74, the drain valve 83, the drain valve 84, the drain valve 85, the delay bed 9 is connected with the pretreatment bed 8, the delay bed 10 is connected with the delay bed 9, the air inlet valve 67 is arranged on an inlet pipe 113 of the pretreatment bed 8, the air inlet valve 70 is arranged on an inlet pipe 114 of the delay bed 9, the air inlet valve 73 is arranged on an inlet pipe 115 of the delay bed 10, the air outlet valve 69 is arranged on a connecting pipe 99 between the pretreatment bed 8 and the delay bed 9, the air outlet valve 72 is arranged on a connecting pipe 100 between the delay bed 9 and the delay bed 10, the air outlet valve 74 is arranged on a connecting pipe 101 between the delay bed 10 and the discharge pressure reducing device, the drain valve 83 is arranged on a drain pipe 116 connected with an outlet of the pretreatment bed 8, a drain line 117 connected to the outlet of the delay bed 9 is provided with a drain valve 84, a drain line 118 connected to the outlet of the delay bed 10 is provided with a drain valve 85, a bypass line 102 connected between the pretreatment bed 8 and the delay bed 9 is provided with a bypass valve 68, a connection bypass line 103 connected between the delay bed 9 and the delay bed 10 is provided with a bypass valve 71, and a bypass line 104 connected between the delay bed 10 and the discharge pressure reducing device is provided with a bypass valve 75.
Specifically, in this embodiment, one pretreatment bed is provided, and a plurality of delay beds are provided, and one of the delay beds is used for standby. In this embodiment, the pretreatment bed 8 is used to further remove water vapor, aerosol, organic matter, and impurities entrained in the exhaust gas, thereby protecting and ensuring the service life of the delay bed 9 and the delay bed 10 and the adsorption retention effect on the radionuclide.
In this embodiment, the pretreatment bed 8, the delay bed 9, and the delay bed 10 may be replaced or repaired by bypassing the bypass valves 68, 71, and 75, if necessary. In order to facilitate the replacement of the medium, the inlet and the outlet of the waste medium are connected by flanges.
In this embodiment, the pretreatment bed 8, the delay bed 9, and the delay bed 10 are all disposed in the same equipment room, and the top of the equipment room is provided with hydrogen concentration monitoring and temperature monitoring to monitor system leakage or discover fire risk as early as possible. The fire resistance limit and the wall thickness of the corresponding room are designed according to the active carbon loading, and valves and instruments which need to be frequently operated are arranged outside the room. And then, in case of fire, the personnel are protected from entering the room for operation.
The connection pipe 99 is provided with a temperature meter 37, the connection pipe 100 is provided with a temperature meter 38, and the connection pipe 101 is provided with a temperature meter 39. When the temperature monitored by any one or more of the temperature meter 37, the temperature meter 38 and the temperature meter 39 is higher than the preset temperature, which indicates that the delayed decay device has a fire risk, a high-temperature alarm is triggered by the temperature meter 37, the temperature meter 38 and the temperature meter 39, the interlock waste gas compressor 2 and the waste gas compressor 3 are automatically stopped, the discharge valve 77 of the interlock system is automatically closed, and the nitrogen fire extinguishing device is triggered to start.
Preferably, the filling media in the pretreatment bed 8, the delay bed 9 and the delay bed 10 are spherical coconut shell activated carbon, so that the pretreatment bed is convenient to replace and has higher adsorption and purification effects on the inert gas fission nuclide krypton and xenon. The bed bodies of the pretreatment bed 8, the delay bed 9 and the delay bed 10 are cylindrical cylinders, the flow speed of exhaust gas in each bed is 0.1-0.5 cm/s, the relative humidity of inlet air is not higher than 20% RH, and the temperature of inlet air is not higher than 20 ℃.
The waste gas inlet, the buffer device, the compression device, the cooling and dehumidifying device, the flame retardant device, the delayed decay device and the discharge pressure reducing device are sequentially connected through pipelines and then are sent to the ventilation filter unit 16 through the radioactivity monitoring instrument 42. The delayed decay device is connected with the nitrogen fire extinguishing device through a pipeline, the related thermometers 37, 38 and 39 trigger alarm signals, the nitrogen is automatically supplied in an interlocking mode, the concentration of hydrogen and oxygen is analyzed on line, the compression device is stopped in an interlocking mode, and the system discharge valve 77 is closed, so that nitrogen annihilation is carried out on the delayed decay device, and fire is extinguished.
The embodiment adopts the combined process design, and with buffer, compressor arrangement, cooling dehydrating unit, fire-retardant device, delayed decay device, discharge pressure relief device in proper order through the effectual connection of pipeline, can realize keeping in the mixing of radioactive waste gas characteristic, improve to the decay effect of detaining such as radionuclide krypton, xenon, can realize the operation of system in succession, stable, high efficiency to it has extensive suitability to treat the fluctuation of exhaust gas pressure or flow or waste gas volume.
In the embodiment, the influence of fluctuations of the inlet characteristic pressure, the flow and the like of the radioactive waste gas is solved through the buffer device, and the steady-state operation of the compression device and the delayed decay device is improved; the compression device is self-protected, so that the damage of the compression device and the risk of overpressure hydrogen leakage of the system are prevented; the cooling and dehumidifying device which can be automatically or manually switched protects and prolongs the service life of the delayed decay device; through nitrogen gas extinguishing device and fire-retardant device, realized that the system puts out a fire fast and prevents that the conflagration from spreading.
The radioactive waste gas treatment system for the nuclear facility in the embodiment greatly improves the purification effect of radioactive waste gas, greatly reduces the size of equipment and the occupied space, reduces the production of secondary waste media, waste water and the like, greatly prevents the system from radioactive leakage to the environment, hydrogen explosion and fire risks, greatly ensures the safety and reliable operation of the system, has strong wide applicability in the field of radioactive waste gas treatment of the nuclear facility, and has high utilization value in the field of the nuclear facility.
It will be understood that the above embodiments are merely exemplary embodiments taken to illustrate the principles of the present invention, which is not limited thereto. It will be apparent to those skilled in the art that various modifications and improvements can be made without departing from the spirit and substance of the utility model, and these modifications and improvements are also considered to be within the scope of the utility model.
Claims (12)
1. A radioactive exhaust treatment system for nuclear facilities, comprising:
a buffer device for receiving and mixing the radioactive waste gas;
the compression device is connected with the buffer device and is used for boosting and cooling the radioactive waste gas;
the delayed decay device is connected with the compression device and is used for delaying decay of the radioactive waste gas and removing water vapor, organic impurities, radioactive aerosol and fission nuclides in the radioactive waste gas;
and a discharge pressure reducing device (14) connected with the delayed decay device and used for reducing the pressure of the radioactive waste gas.
2. The radioactive exhaust gas treatment system for nuclear facilities, according to claim 1, further comprising:
a flame retardant device comprising: the flame retardant device comprises a first flame retardant device (12) arranged at the inlet of the delayed decay device and a second flame retardant device (13) arranged at the outlet of the delayed decay device, wherein the flame retardant device is used for retarding flame.
3. The radioactive exhaust gas treatment system for nuclear facilities, according to claim 1, further comprising:
the dehumidifying device is arranged between the compressing device and the delayed decay device, is respectively connected with the compressing device and the delayed decay device, and is used for removing condensed water of compressed waste gas discharged from the compressing device and reducing absolute humidity in the compressed waste gas.
4. A radioactive exhaust gas treatment system for nuclear facilities, according to claim 3, wherein the dehumidifying apparatus comprises: the device comprises a steam-water separator (6), a liquid level meter (35), a pressure meter (34), a gas outlet valve (58), a humidity monitoring meter (36), a dehumidification bed (7), a bypass valve (65), an air inlet valve (64), an air outlet valve (66), a drain valve (59) and a drain valve (82); the steam-water separator (6) is connected with the compression device, the steam-water separator (6) is used for removing condensed water of compressed waste gas discharged from the compression device, the liquid level instrument (35) is connected with the steam-water separator (6), and the pressure instrument (34) is connected with the steam-water separator (6); the dehumidification bed (7) is connected with the steam-water separator (6), the dehumidification bed (7) is also connected with the delayed decay device, the dehumidification bed (7) is used for reducing the absolute humidity in the compressed waste gas, the device is characterized in that a gas outlet valve (58) and a humidity monitoring instrument (36) are arranged on a connecting pipeline (105) between the dehumidification bed (7) and an outlet of the steam-water separator (6), a drain valve (59) is arranged on a drain pipeline (106) connected with an outlet of the steam-water separator (6), a drain valve (82) is arranged on a drain pipeline (107) connected with an outlet of the dehumidification bed (7), a bypass valve (65) is arranged on a bypass pipeline (108) connected between the dehumidification bed (7) and the delayed decay device, an air inlet valve (64) is arranged on a connecting pipeline (109) at an inlet of the dehumidification bed (7), and an air outlet valve (66) is arranged on a connecting pipeline (110) between the dehumidification bed (7) and the delayed decay device.
5. The radioactive exhaust gas treatment system for nuclear facilities, according to claim 1, further comprising:
on-line sampling cabinet (11), with buffer entrance connection, on-line sampling cabinet (11) are used for the radioactive waste gas sample of buffer entry and to hydrogen concentration, oxygen concentration carries out continuous monitoring, on-line sampling cabinet (11) still with delay decay device entry, delay decay device exit linkage, on-line sampling cabinet (11) still are used for the radioactive waste gas sample of delay decay device entry, the export of delay decay device and to hydrogen concentration, oxygen concentration carries out continuous monitoring.
6. The radioactive exhaust gas treatment system for nuclear facilities, according to claim 1, further comprising:
and the nitrogen fire extinguishing device is connected with the inlet of the delayed decay device and is used for extinguishing fire.
7. A radioactive exhaust gas treatment system for nuclear power plant according to claim 6, wherein the nitrogen fire extinguishing device includes: a nitrogen source (19), an inlet pressure gauge (40), a decompression regulating valve (76), a nitrogen gas supply valve (60) and a safety valve (61), wherein the nitrogen source (19) is connected with an inlet of the delayed decay device, the inlet pressure gauge (40) and the nitrogen gas supply valve (60) are arranged on a connecting pipeline (111) between the nitrogen source (19) and the inlet of the delayed decay device, an outlet of the inlet pressure gauge (40) close to the nitrogen source (19) is used for detecting the pressure of the nitrogen source, a branch pipeline (93) is connected on the connecting pipeline (111) between the nitrogen source (19) and the inlet of the delayed decay device and is connected with an outlet pipeline (112) of a discharge decompression device (14), the decompression regulating valve (76) is arranged on the branch pipeline (93), a branch pipeline (94) is arranged on a pipeline between the nitrogen gas supply valve (60) and the nitrogen source (19), and the safety valve (61) is arranged on the branch pipeline (94), the branch duct (94) is used for connecting the chimney (20).
8. A radioactive exhaust gas treatment system for nuclear power plant according to claim 1, wherein the buffer device includes: an air inlet valve (46), a buffer storage tank (1), a nitrogen source (17), a nitrogen supply valve (47), a safety valve (48), a chimney (20) and a drain valve (86), wherein the buffer storage tank (1) is connected with an air inlet pipeline (95), the device is connected with a radioactive waste gas inlet (15) through an air inlet pipeline (95), an air inlet valve (46) is arranged on the air inlet pipeline (95), a branch pipeline (96) is arranged on the air inlet pipeline (95), the branch pipeline (96) is connected with a nitrogen source (17), a nitrogen gas supply valve (47) is arranged on the branch pipeline (96), an overpressure release pipeline (97) is arranged on the air inlet pipeline (95), the overpressure release pipeline (97) is connected with a chimney (20), a safety valve (48) is arranged on the overpressure release pipeline (97), and a drain valve (86) is arranged on a drain pipeline (98) connected with an outlet of a buffer storage tank (1).
9. The radioactive exhaust gas treatment system for nuclear facilities, according to claim 1, wherein the compressing means includes: the first compression device and the second compression device are connected in parallel, the first compression device and the second compression device are respectively connected with the buffer device and the delayed decay device, and the first compression device and the second compression device are used for one by one.
10. The radioactive exhaust gas treatment system for nuclear facilities, according to claim 9, wherein the first compression means includes: the device comprises an air inlet valve (52), a pressure gauge (28), a filter (91), an exhaust gas compressor (2), a compressed exhaust gas cooler (4), a thermometer (30), a pressure gauge (32) and a compressed gas discharge valve (54) which are sequentially connected, wherein the air inlet valve (52) is connected with a buffer device, and the compressed gas discharge valve (54) is connected with a delayed decay device;
the second compressing device includes: the device comprises an air inlet valve (53), a pressure gauge (29), a filter (92), an exhaust gas compressor (3), a compressed exhaust gas cooler (5), a thermometer (31), a pressure gauge (33) and a compressed gas discharge valve (55) which are sequentially connected, wherein the air inlet valve (53) is connected with a buffer device, and the compressed gas discharge valve (55) is connected with a delayed decay device.
11. The radioactive exhaust gas treatment system for nuclear facilities, according to claim 1, wherein the delayed decay apparatus comprises: a pretreatment bed (8), a delay bed (9), a delay bed (10), a bypass valve (68), a bypass valve (71), a bypass valve (75), an air inlet valve (67), an air inlet valve (70), an air inlet valve (73), an air outlet valve (69), an air outlet valve (72), an air outlet valve (74), a drain valve (83), a drain valve (84) and a drain valve (85), wherein the delay bed (9) is connected with the pretreatment bed (8), the delay bed (10) is connected with the delay bed (9), the air inlet valve (67) is arranged on an inlet pipeline (113) of the pretreatment bed (8), the air inlet valve (70) is arranged on an inlet pipeline (114) of the delay bed (9), the air inlet valve (73) is arranged on an inlet pipeline (115) of the delay bed (10), the air outlet valve (69) is arranged on a connecting pipeline (99) between the pretreatment bed (8) and the delay bed (9), and the air outlet valve (72) is arranged on a connecting pipeline (100) between the delay bed (9) and the delay bed (10), an air outlet valve (74) is arranged on a connecting pipeline (101) between the delay bed (10) and the discharge pressure reducing device (14), a drain valve (83) is arranged on a drain pipeline (116) connected with the outlet of the pretreatment bed (8), a drain valve (84) is arranged on a drain pipeline (117) connected with the outlet of the delay bed (9), a drain valve (85) is arranged on a drain pipeline (118) connected with the outlet of the delay bed (10), a bypass valve (68) is arranged on a bypass pipeline (102) connected between the pretreatment bed (8) and the delay bed (9), a bypass valve (71) is arranged on a connecting bypass pipeline (103) between the delay bed (9) and the delay bed (10), and a bypass valve (75) is arranged on a bypass pipeline (104) connected between the delay bed (10) and the discharge pressure reducing device (14).
12. The radioactive waste gas treatment system for nuclear facilities, according to claim 11, wherein the packing media in the pretreatment bed (8), the delay bed (9) and the delay bed (10) are spherical coconut shell activated carbon.
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN112162309A (en) * | 2020-08-13 | 2021-01-01 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Cabinet type air-borne radioactive integrated monitoring device |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112162309A (en) * | 2020-08-13 | 2021-01-01 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Cabinet type air-borne radioactive integrated monitoring device |
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