CN103474121A - Radioactive waste gas treatment system for nuclear power plant - Google Patents
Radioactive waste gas treatment system for nuclear power plant Download PDFInfo
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- CN103474121A CN103474121A CN2013104400899A CN201310440089A CN103474121A CN 103474121 A CN103474121 A CN 103474121A CN 2013104400899 A CN2013104400899 A CN 2013104400899A CN 201310440089 A CN201310440089 A CN 201310440089A CN 103474121 A CN103474121 A CN 103474121A
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Abstract
The invention relates to a radioactive waste gas treatment system for a nuclear power plant. The radioactive waste gas treatment system comprises a gas cooler, a gas-water separator, a protecting bed, dwelling beds and a radioactive monitoring device which are sequentially connected through a pipeline. The radioactive waste gas treatment system further comprises a hot nitrogen gas source, wherein the protecting bed is a silica-gel drying bed, the silica-gel drying bed is provided with a hot nitrogen gas purge interface, and the hot nitrogen gas purge interface is connected with the hot nitrogen gas source. According to the radioactive waste gas treatment system for the nuclear power plant, an online-renewable silica gel bed drying manner is used, so that the generation of radioactive secondary wastes is reduced effectively, and the operating cost resulting from waste treatment and new silica gel replacement is avoided; meanwhile, due to a water sealing pipe, the potential risk of radioactive hydrogen-containing waste gas leakage caused by valve misoperation during normal operation, untimely valve shutoff before operation and untight sealing can be avoided, and the service life of main equipment is prolonged.
Description
Technical field
The present invention relates to the processing of nuclear power station radioactive emission, in particular, relate to a kind of nuclear power station Spent Radioactive gas processing system that uses activated charcoal to be detained decay.
Background technology
The nuclear power station reactor core can produce radioactive nuclide when nuclear fission is reacted, and as Xe, Kr etc., during these fission products can leak into reactor coolant when clad failure, and arrives a whole loop with the water sport diffusion mobility; Along with the variation of temperature, pressure, radioactive fission gas can be separated out and entered gas-phase space and form radioactive emission from cooling medium, and this type of waste gas just can discharge after usually need to processing in environment.
At present, the processing for above-mentioned radioactive emission mainly adopts pressurization to store decay and two kinds of modes of activated charcoal delay decay.Pressurization storage decay technique mainly comprises the deaeration tower of pressurizer relief tank, reactor coolant drain tank, appearance control case and boron recovery system etc., the radioactive emission that is stored in blanketing gas, purging exhaust and the maintenance exhaust etc. of the container of circuit cools agent is sent into surge tank after collecting, after surge tank arrives certain pressure, the downstream compressor automatic linkage starts, the waste gas positive delivery is stored to delay tank, by the short-lived nuclides such as Xe, Kr are stored to decay, reduce its radioactive level.Waste gas after decay after sample analysis is up to standard, by power plant's ventilating system to environmental emission.
But above-mentioned technique is by the exhaust gases upstream storage of pressurizeing, the gaseous radioactivity activity concentration after being concentrated increases greatly, and hig pressure storage strengthens the risk of radioactive leak, and increases difficulty and the cost of personnel's radiation protection and shielding; Secondly, because of density of hydrogen in waste gas to be decayed is higher, there are the security risks such as hydrogen is quick-fried, leakage in hig pressure storage for a long time, increases design difficulty and the costs such as fire-proof and explosion-proof, ventilation, fire-fighting simultaneously; This technological requirement is equipped with corresponding pressue device, and as compressor, surge tank, this has not only increased cost and energy consumption, also makes the operation of system control more complicated; In addition, the delay tank volume is larger, need take more factory building space.
Be detained in decay technique at activated charcoal, after the waste gas that up-stream system produces enters exhaust treatment system, first through subcooler, carry out gas cooled, reduce exhaust gas temperature and remove the moisture that condensation goes out, reach the effect of predrying gas.The liquid that condensation goes out is collected in moisture trap.Waste gas after cooling enters activated charcoal protection bed, and the moisture in this waste gas is further removed.Activated charcoal protection bed downstream is that activated charcoal is detained bed, and in this waste gas, the short-lived nuclides such as Xe, Kr are adsorbed delay, and decay reduces its radioactive level.After the radioactivity monitoring is up to standard, waste gas passes through power plant's ventilating system to environmental emission.
But; absorbent charcoal material is comparatively responsive to humidity; activated charcoal absorption property after making moist decreases and even lost efficacy; may cause exhaust treatment system and up-stream system to be stopped transport; therefore it is the key factor that affects activated charcoal life-span and system availability that waste gas humidity is controlled; even be provided with activated charcoal protection bed in a delay bed upstream; gas after the gas cooler cooling is further dehumidified; activated charcoal still can be little and saturated because of water absorption capacity; regeneration frequency is higher, and activated charcoal is general to the effect on moisture extraction of low humidity gas.Activated charcoal needs the equipment that shifts out to carry out drying or replacing after inefficacy, has increased the generation of charge and discharge operations and secondary refuse.
Simultaneously, the moisture trap in gas cooler downstream is provided with liquid level and controls, and in the keying of water discharging valve and moisture trap, liquid level signal is chain, opens valve downstream when liquid level is high water is discharged, and closes water discharging valve when liquid level is low.As failsafe valve or personnel's maloperation, vessel liquid will all be discharged, and the hydrogeneous waste gas of radioactivity may be by water discharge line to the system external leakage.Stop transport between turn(a)round in system, need open water discharging valve by emptying rate of liquid, if fail timely valve-off before the recovery system operation, have equally the security risk of the hydrogeneous exhaust gas leakage of radioactivity.
Although all there is defect separately in above-mentioned two kinds of processing modes, but from multianalysiss such as security of system, operation ease and space savings, activated charcoal is detained decay technique and all is better than pressurization storage decay technique, but activated charcoal needs the equipment that shifts out to carry out the problems such as drying or replacing after easily losing efficacy and losing efficacy, still affects the use that activated charcoal is detained the technique that decays.
Summary of the invention
Technical matters to be solved by this invention is; a kind of nuclear power station Spent Radioactive gas processing system that uses activated charcoal to be detained decay is provided; solve activated charcoal protection bed water absorption capacity little, change problem frequently, solve the problem of the easy maloperation of moisture trap simultaneously.
In nuclear power station Spent Radioactive gas processing system of the present invention; comprise the gas cooler, moisture trap, protection bed, delay bed, the radiological measuring device that connect successively by pipeline; described Spent Radioactive gas processing system also includes the hot nitrogen source; described protection bed is the silica dehydrator bed; be provided with hot nitrogen on described silica dehydrator bed and purge interface, described hot nitrogen purges interface and is connected with described hot nitrogen source.
In nuclear power station Spent Radioactive gas processing system of the present invention, described Spent Radioactive gas processing system also includes dip pipe, and an end of described dip pipe is connected with the draining valve of described moisture trap below, and the other end freeing port of described dip pipe is connected.
In nuclear power station Spent Radioactive gas processing system of the present invention, described Spent Radioactive gas processing system also comprises at least one air hatch, and described air hatch is connected with the oxygen concentration tester of gas oxygen concentration in the serial sampling analytic system.
In nuclear power station Spent Radioactive gas processing system of the present invention, in described Spent Radioactive gas processing system, maintain pressure-fired.
In nuclear power station Spent Radioactive gas processing system of the present invention, on the floss hole of described Spent Radioactive gas processing system, be provided with non-return valve.
In nuclear power station Spent Radioactive gas processing system of the present invention, the U-bend that described dip pipe is inner water-filling or W shape bend pipe.
In nuclear power station Spent Radioactive gas processing system of the present invention, also be provided with water funnel above described dip pipe.
In nuclear power station Spent Radioactive gas processing system of the present invention, the described dip pipe outside also is provided with the visor of liquid level in the described dip pipe of observation.
In nuclear power station Spent Radioactive gas processing system of the present invention, described Spent Radioactive gas processing system also includes source nitrogen, and described source nitrogen is connected with the pipeline in downstream, radiological measuring device gas outlet with the pipeline of described gas cooler air intake opening upstream respectively.
In nuclear power station Spent Radioactive gas processing system of the present invention, described Spent Radioactive gas processing system also includes nitrogen heater, the nitrogen that described source nitrogen flows out purges interface with the described hot nitrogen of described silica dehydrator bed and is connected after described nitrogen heater heating, and the described source nitrogen after heating is described hot nitrogen source.
Nuclear power station Spent Radioactive gas processing system of the present invention, but adopt the silica gel bed drying mode of on-line regeneration, effectively reduce the generation of radioactivity secondary refuse, saving refuse processes and more renews the operating cost of silica gel, simultaneously, dip pipe is set up in the draining valve of moisture trap below, and valve misoperation while avoiding normally moving, the early gate that puts into operation are not closed and the potential risk of poorly sealed the caused hydrogeneous exhaust gas leakage of radioactivity in time, extends the serviceable life of major equipment.
The accompanying drawing explanation
In order to be illustrated more clearly in the technical scheme in the embodiment of the present invention, in below describing embodiment, the accompanying drawing of required use is briefly described, apparently, accompanying drawing in the following describes is only one embodiment of the present of invention, for those of ordinary skills, under the prerequisite of not paying creative work, can also obtain according to these accompanying drawings other accompanying drawing.
Fig. 1 is the structural representation of nuclear power station Spent Radioactive gas processing system of the present invention.
Embodiment
Below in conjunction with accompanying drawing, the technical scheme in the embodiment of the present invention is clearly and completely described, obviously, described embodiment is only the present invention's part embodiment, rather than whole embodiment.Embodiment based in the present invention, those of ordinary skills, not making under the creative work prerequisite the every other embodiment obtained, belong to the scope of protection of the invention.
Nuclear power station Spent Radioactive gas processing system of the present invention, comprise gas cooler 10, moisture trap 20, silica dehydrator bed 30, be detained bed 40, radiological measuring device 50, each radioactive emission of gas cooler 10 and system upstream produces source 11 as nuclear reactor etc. and is connected, moisture trap 20, silica dehydrator bed 30, be detained beds 40, after radiological measuring device 50 is connected in gas cooler 10 by pipeline successively.Radioactive emission reduces gas temperature by heat interchange after entering gas cooler 10, and removes the moisture of condensation, reaches pre-dried effect.Cooled gas separates in moisture trap 20 with the liquid of separating out, and isolated liquid is discharged from freeing port, is collected into rear unified processing of collecting pit 74.The water discharging valve downstream of moisture trap 20 is provided with the dip pipe (not shown), the U-bend that dip pipe is inner water-filling or W shape bend pipe, also can form the bend pipe of water seal for other shape, when moisture trap 20 draining, even isolation valve fails to cut out in time, dip pipe still can form one water seal, prevents that radioactive emission from leaking through this drainpipe.Preferably, dip pipe is transparent pipe, also be provided with the visor 72 of liquid level in the observation water tube sealing in the outside of dip pipe, position as of living in as dip pipe in Fig. 1 and visor 72 are overlapping, the water inlet of dip pipe is connected with the water discharging valve of moisture trap 20, the water delivering orifice of dip pipe is connected with collecting pit 74, also is provided with water funnel 73 above dip pipe, and the water delivering orifice of water funnel 73 is connected with the water inlet of dip pipe.Liquid when system overhaul in moisture trap 20 and dip pipe is all emptying, before system comes into operation again by water funnel 73 to water filling in dip pipe, and by visor 72 observation liquid levels, after guaranteeing again to form water seal, come into operation again, even isolation valve fails to cut out in time like this, dip pipe still can form one water seal, prevents that radioactive emission from leaking through this drainpipe.
After moisture trap 20 is realized gas-water separation, radioactive emission enters the further removal moisture drying of a silica dehydrator bed 30, prevents that the moisture of carrying secretly from entering delay bed 40, causes delay bed 40 to make moist and hydraulic performance decline.After system operation a period of time, silica gel is even saturated because of the accumulation hydraulic performance decline of moisture, if directly changed, useless silica gel need be processed as radioactive waste, has increased charge and discharge operations, secondary refuse processing cost and has more renewed the expense of silica gel.Nuclear power station Spent Radioactive gas processing system of the present invention solves the problems of the technologies described above by useless silica gel is carried out to on-line regeneration, be provided with hot nitrogen on silica dehydrator bed 30 and purge the interface (not shown), in system stoppage in transit gap, purge interface by above-mentioned hot nitrogen and pass into heated nitrogen to silica dehydrator bed 30, hot nitrogen is taken the moisture of silica gel adsorption to make the silica gel restorability out of, purge gas is discharged and is entered the nuclear power station ventilating system from hot nitrogen escape hole 63, after treatment to environmental emission.
Radioactive emission is after silica dehydrator bed 30 dryings, the radioactive emission of low humidity enters and is detained bed 40, be detained bed 40 for being full of the snake pipe of activated charcoal, radioelement in radioactive emission at this by the activated charcoal Dynamic Adsorption, separate with carrier gas such as hydrogen, nitrogen gradually, reach the effect that radioelement is detained.Be trapped in the radioelement be detained in bed 40 and constantly decay, radioactive level is minimized, preferred, can arrange and interconnect a plurality of effects that bed 40 has reached better delay radioelement of being detained.
Through the radioactive emission that is detained decay, before being sent to the discharge of nuclear power station ventilating system, need through radioactivity monitoring, therefore be provided with radiological measuring device 50 being detained between bed 40 and floss hole 82, if the radioactivity monitored higher than setting value the isolation valve of closing floss hole 82 to stop exhaust.Due to the hydrogen that the gas of discharging from floss hole 82 contains higher concentration, so too low in the dilution flow rate of ventilating system, be also should close the isolation valve of floss hole 82, prevent that hydrogen from accumulating in the ventilation duct of ventilating system.
The hydrogen that contains higher concentration in radioactive emission due to nuclear power station, avoid hydrogen-oxygen to mix the danger that produces blast, preferably, nuclear power station Spent Radioactive gas processing system of the present invention also comprises at least one air hatch, air hatch can be arranged on any position of system pipeline of the present invention, air hatch is connected with the oxygen concentration tester, the oxygen concentration tester can the serial sampling analytic system in the gas oxygen concentration, simultaneously, nuclear power station Spent Radioactive gas processing system of the present invention also comprises source nitrogen 60, source nitrogen 60 is connected with the second nitrogen access port 62 with the first nitrogen access port 61 respectively, the first nitrogen access port 61 is arranged on the pipeline of gas cooler 10 air intake opening upstreams, the second nitrogen access port 62 is arranged on the pipeline in radiological measuring device 50 downstreams, gas outlet, when in system, gas oxygen concentration content surpasses preset value, by source nitrogen 60, to the first nitrogen access port 61 nitrogen injections, the whole system loop is diluted, reduce oxygen concentration, when in system, gas oxygen concentration content surpasses default dangerous values, by source nitrogen 60 to the first nitrogen access port 61 and the second nitrogen access port 62 nitrogen injection simultaneously, emphasis dilution Exhaust Gas in the time of dilution whole system loop, avoid gas oxygen concentration in ventilating system become suddenly large and blast and wait danger.
Spent Radioactive gas processing system of the present invention maintains pressurized operation, on the floss hole 82 of simultaneity factor, is provided with non-return valve 81, can prevent that air from entering native system and forming the flammable explosive gas that hydrogen-oxygen mixes.Special needs to be pointed out is, radiological measuring device 50 and oxygen concentration tester all are electrically connected to master controller, when the radioactivity that radiological measuring device 50 monitors is closed the isolation valve of floss hole 82 automatically higher than setting value by master controller; In like manner, when the oxygen concentration content detected when the oxygen concentration tester surpasses preset value, the valve that master controller is controlled the first nitrogen access port 61 upstreams is automatically opened and is realized that subtend whole system loop is filled with nitrogen, reduces oxygen concentration; Intrasystem pressure-fired also can be controlled automatically by master controller, open the isolation valve exhaust of floss hole 82 when intrasystem air pressure being detected higher than preset value, the isolation valve of cutting out floss hole 82 when intrasystem air pressure being detected lower than preset value gos up internal system air pressure.
Preferably, Spent Radioactive gas processing system of the present invention also includes the nitrogen heater (not shown), the nitrogen flowed out from source nitrogen 60 purges interface with the hot nitrogen of silica dehydrator bed 30 and is connected after the nitrogen heater heating, the on-line regeneration of realization to silica dehydrator bed 30, the source nitrogen 60 after heating is the hot nitrogen source.
Claims (10)
1. a nuclear power station Spent Radioactive gas processing system; comprise the gas cooler, moisture trap, protection bed, delay bed, the radiological measuring device that connect successively by pipeline; it is characterized in that; described Spent Radioactive gas processing system also includes the hot nitrogen source; described protection bed is the silica dehydrator bed; be provided with hot nitrogen on described silica dehydrator bed and purge interface, described hot nitrogen purges interface and is connected with described hot nitrogen source.
2. Spent Radioactive gas processing system according to claim 1, it is characterized in that, described Spent Radioactive gas processing system also includes dip pipe, and an end of described dip pipe is connected with the draining valve of described moisture trap below, and the other end of described dip pipe is connected with freeing port.
3. Spent Radioactive gas processing system according to claim 2, is characterized in that, described Spent Radioactive gas processing system also comprises at least one air hatch, and described air hatch is connected with the oxygen concentration tester of gas oxygen concentration in the serial sampling analytic system.
4. Spent Radioactive gas processing system according to claim 3, is characterized in that, in described Spent Radioactive gas processing system, maintains pressure-fired, prevents that air from entering.
5. Spent Radioactive gas processing system according to claim 3, is characterized in that, on the floss hole of described Spent Radioactive gas processing system, is provided with non-return valve.
6. Spent Radioactive gas processing system according to claim 3, is characterized in that, the U-bend that described dip pipe is inner water-filling or W shape bend pipe.
7. Spent Radioactive gas processing system according to claim 3, is characterized in that, also is provided with water funnel above described dip pipe.
8. Spent Radioactive gas processing system according to claim 3, is characterized in that, the described dip pipe outside also is provided with the visor of liquid level in the described dip pipe of observation.
9. Spent Radioactive gas processing system according to claim 3, it is characterized in that, described Spent Radioactive gas processing system also includes source nitrogen, and described source nitrogen is connected with the pipeline in downstream, radiological measuring device gas outlet with the pipeline of described gas cooler air intake opening upstream respectively.
10. Spent Radioactive gas processing system according to claim 9, it is characterized in that, described Spent Radioactive gas processing system also includes nitrogen heater, the nitrogen that described source nitrogen flows out purges interface with the described hot nitrogen of described silica dehydrator bed and is connected after described nitrogen heater heating, and the described source nitrogen after heating is described hot nitrogen source.
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104143368A (en) * | 2014-08-12 | 2014-11-12 | 中广核工程有限公司 | Nuclear power station radioactive waste gas treatment system |
| CN104216001A (en) * | 2014-08-16 | 2014-12-17 | 中国船舶重工集团公司第七一九研究所 | Sampling-type radiation monitoring device for high-humidity gases |
| CN105355249A (en) * | 2015-11-16 | 2016-02-24 | 中广核工程有限公司 | Radioactive waste gas processing device for nuclear power station |
| CN105575452A (en) * | 2014-10-13 | 2016-05-11 | 中国辐射防护研究院 | Application method for drying agent in silica gel drying unit of inert gas retention system |
| CN106378257A (en) * | 2016-11-17 | 2017-02-08 | 无锡大功机械制造有限公司 | Waste gas conveying dust removing pipe |
| CN107289733A (en) * | 2017-07-18 | 2017-10-24 | 佛山市鼎特机械设备有限公司 | A kind of sterile liquid nitrogen machine and its nitrogen producing craft flow |
| CN109166641A (en) * | 2018-09-30 | 2019-01-08 | 岭东核电有限公司 | Low-level Spent Radioactive gas processing system in a kind of lead bismuth heap |
| CN109300563A (en) * | 2018-10-15 | 2019-02-01 | 江苏核电有限公司 | A kind of nuclear power station Spent Radioactive gas processing system water seal arrangement |
| CN110097991A (en) * | 2018-01-31 | 2019-08-06 | 中国辐射防护研究院 | Removable radioactive gas recovery system is used under a kind of emergency conditions |
| CN110335688A (en) * | 2019-06-27 | 2019-10-15 | 山东普瑞普勒能源科技有限公司 | A kind of tandem heat exchanger Spent Radioactive air cooling system |
| CN110444309A (en) * | 2018-01-29 | 2019-11-12 | 中国辐射防护研究院 | A kind of nuclear facilities radioactivity technology waste gas processing system |
| CN111710453A (en) * | 2020-06-18 | 2020-09-25 | 中核环保产业有限公司 | Method for treating radioactive waste gas of nuclear power station |
| CN112717625A (en) * | 2020-11-23 | 2021-04-30 | 岭东核电有限公司 | Hydrogen-containing waste gas treatment system of nuclear power station |
| 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 |
| CN115193216A (en) * | 2022-07-15 | 2022-10-18 | 江苏希捷新能源工程技术有限公司 | A nuclear power plant waste gas treatment system based on activated carbon delayed bed and its use method |
Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN2826396Y (en) * | 2005-08-23 | 2006-10-11 | 北京吉天仪器有限公司 | Low-vapor natural waste chemical gas phase generating gas-liquid separation device |
| CN201375899Y (en) * | 2009-02-23 | 2010-01-06 | 宝山钢铁股份有限公司 | Allochroic silicagel regeneration unit |
| CN101814326A (en) * | 2010-04-12 | 2010-08-25 | 江苏宝宸净化设备有限公司 | Pressure water reactor nuclear power plant high-radioactivity waste gas normal-temperature delay treatment complete equipment |
| CN101847456A (en) * | 2009-06-24 | 2010-09-29 | 中广核工程有限公司 | Waste gas treatment method of nuclear power plant and treatment device thereof |
| JP2011018534A (en) * | 2009-07-08 | 2011-01-27 | Panasonic Corp | Fuel cell system |
| CN203196510U (en) * | 2013-03-22 | 2013-09-18 | 扬州市恒通环保科技有限公司 | Nitrogen desorption device |
| CN203456108U (en) * | 2013-09-24 | 2014-02-26 | 中广核工程有限公司 | Radioactive waste gas treatment system for nuclear power station |
-
2013
- 2013-09-24 CN CN201310440089.9A patent/CN103474121B/en active Active
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN2826396Y (en) * | 2005-08-23 | 2006-10-11 | 北京吉天仪器有限公司 | Low-vapor natural waste chemical gas phase generating gas-liquid separation device |
| CN201375899Y (en) * | 2009-02-23 | 2010-01-06 | 宝山钢铁股份有限公司 | Allochroic silicagel regeneration unit |
| CN101847456A (en) * | 2009-06-24 | 2010-09-29 | 中广核工程有限公司 | Waste gas treatment method of nuclear power plant and treatment device thereof |
| JP2011018534A (en) * | 2009-07-08 | 2011-01-27 | Panasonic Corp | Fuel cell system |
| CN101814326A (en) * | 2010-04-12 | 2010-08-25 | 江苏宝宸净化设备有限公司 | Pressure water reactor nuclear power plant high-radioactivity waste gas normal-temperature delay treatment complete equipment |
| CN203196510U (en) * | 2013-03-22 | 2013-09-18 | 扬州市恒通环保科技有限公司 | Nitrogen desorption device |
| CN203456108U (en) * | 2013-09-24 | 2014-02-26 | 中广核工程有限公司 | Radioactive waste gas treatment system for nuclear power station |
Non-Patent Citations (1)
| Title |
|---|
| 林诚格: "《非能动安全先进压水堆核电技术（中册）》", 31 May 2010, article "AP1000核电厂辅助系统", pages: 679-981 * |
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| CN104143368B (en) * | 2014-08-12 | 2017-01-25 | 中广核工程有限公司 | Nuclear power station radioactive waste gas treatment system |
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| CN105355249A (en) * | 2015-11-16 | 2016-02-24 | 中广核工程有限公司 | Radioactive waste gas processing device for nuclear power station |
| CN106378257A (en) * | 2016-11-17 | 2017-02-08 | 无锡大功机械制造有限公司 | Waste gas conveying dust removing pipe |
| CN107289733A (en) * | 2017-07-18 | 2017-10-24 | 佛山市鼎特机械设备有限公司 | A kind of sterile liquid nitrogen machine and its nitrogen producing craft flow |
| CN110444309A (en) * | 2018-01-29 | 2019-11-12 | 中国辐射防护研究院 | A kind of nuclear facilities radioactivity technology waste gas processing system |
| CN110097991B (en) * | 2018-01-31 | 2023-07-14 | 中国辐射防护研究院 | Movable radioactive gas treatment system used under accident condition |
| CN110097991A (en) * | 2018-01-31 | 2019-08-06 | 中国辐射防护研究院 | Removable radioactive gas recovery system is used under a kind of emergency conditions |
| CN109166641B (en) * | 2018-09-30 | 2020-09-18 | 岭东核电有限公司 | Low-level radioactive waste gas treatment system in lead bismuth reactor |
| CN109166641A (en) * | 2018-09-30 | 2019-01-08 | 岭东核电有限公司 | Low-level Spent Radioactive gas processing system in a kind of lead bismuth heap |
| CN109300563A (en) * | 2018-10-15 | 2019-02-01 | 江苏核电有限公司 | A kind of nuclear power station Spent Radioactive gas processing system water seal arrangement |
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| CN111710453A (en) * | 2020-06-18 | 2020-09-25 | 中核环保产业有限公司 | Method for treating radioactive waste gas of nuclear power station |
| CN112717625A (en) * | 2020-11-23 | 2021-04-30 | 岭东核电有限公司 | Hydrogen-containing waste gas treatment system of nuclear power station |
| 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 |
| CN115193216A (en) * | 2022-07-15 | 2022-10-18 | 江苏希捷新能源工程技术有限公司 | A nuclear power plant waste gas treatment system based on activated carbon delayed bed and its use method |
| CN115193216B (en) * | 2022-07-15 | 2023-08-25 | 江苏希捷新能源工程技术有限公司 | Nuclear power station waste gas treatment system based on activated carbon delay bed and application method thereof |
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