CN101847456A - Waste gas treatment method of nuclear power plant and treatment device thereof - Google Patents
Waste gas treatment method of nuclear power plant and treatment device thereof Download PDFInfo
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- CN101847456A CN101847456A CN200910108272A CN200910108272A CN101847456A CN 101847456 A CN101847456 A CN 101847456A CN 200910108272 A CN200910108272 A CN 200910108272A CN 200910108272 A CN200910108272 A CN 200910108272A CN 101847456 A CN101847456 A CN 101847456A
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Abstract
The invention relates to a waste gas treatment method of a nuclear power plant and a treatment device thereof. The treatment method comprises the following steps of: removing the water vapor in the waste gas; decaying radionuclide retention; and retaining the decaying radionuclide by passing the waste gas after the water removal through the active carbon retention bed. The method reduces the circulation speed of the radionuclide, so that the radionuclide is retained in the active carbon in the decaying case and decays therein. The treatment device of the invention comprises a cooler, a vapor/water separator and an active carbon retention bed which is connected with the vapor/water separator and held in at least one decaying case, wherein the cooler, the vapor-water separator and the active carbon retention bed are sequentially connected. The work performance of the active carbon is greatly improved by removing water. The treatment device has simple structure, small volume, little leakage and less danger, via the active carbon retention bed held in at least one decaying case.
Description
Technical field
The present invention relates to a kind of waste gas processing method and treating apparatus thereof, more particularly, relate to a kind of waste gas treatment method of nuclear power plant and treating apparatus thereof.
Background technology
Along with the development of society, people constantly strengthen environmental protection consciousness, and the national policy rules are also being continually strengthened environment requirement, and it requires to improve constantly with standard to treatment of waste gas.Nuclear power station requires also improving constantly to treatment of waste gas.
(CPR1000 is that China Guangdong Nuclear Power Group Co., Ltd. is introducing, digests, absorbing on the basis of advanced foreign technology to existing C PR1000 nuclear power station, in conjunction with " two generations added " million kilowatt compressed water reactor nuclear power technology of gradual improvement over more than 20 years and autonomous innovation formation.) the treatment of waste gas system that contains radioactive nuclide is adopted the compressor waste gas compression that throughput ratio is bigger usually, and then send into that delay tank is airtight to decay, after storing about 45 days to 60 days, when the radioactive level of radioactive nuclide in the delay tank reaches emission request, the operator opens the delay tank bleed valve, waste gas is discharged into the nuclear auxiliary building ventilating system to emit again.Referring to Fig. 1, it is a kind of structural representation of nuclear power station exhaust treatment system in the prior art.Compressor is compressed to 650KPa with waste gas usually, is pressed into delay tank at last and stores.Because waste gas is more, flow is bigger, and delay tank is closed system, so compressor and huge pressurization delay tank need be set with process nuclear waste gas.For example, prior art is provided with 4 18m usually
3With 4 60m
3Delay tank.Like this, make that the disposal system volume is big, take up space and high pressure easily causes gas leakage, the gas that has radioactive nuclide can bring very big harm to people.And it also needs to make total system complicated more in conjunction with ventilating system.
Summary of the invention
The technical problem to be solved in the present invention is, easy gas leakage is brought the defective that danger and exhaust treatment system complexity, volume take up space greatly during at the above-mentioned nuclear power station exhaust-gas treatment of prior art, provides a kind of and handle conveniently, is difficult for revealing gas, dangerous little waste gas treatment method of nuclear power plant.
The technical solution adopted for the present invention to solve the technical problems is: construct a kind of waste gas treatment method of nuclear power plant, may further comprise the steps:
A, anhydrate: remove the steam in the waste gas;
B, delay decay radioactive nuclide: the waste gas after will anhydrating is detained bed to be detained the radioactive nuclide that decays by activated charcoal.
In waste gas treatment method of nuclear power plant of the present invention, also comprise cushioning balance pressure before the described steps A: nuclear power station waste gas is fed in the surge tank carry out the stream pressure balance.
In waste gas treatment method of nuclear power plant of the present invention, described steps A comprises:
A1, condensing water vapor: waste gas is fed refrigeratory carry out condensation and make steam be condensed into liquid;
A2, carbonated drink are separated: will feed steam-water separator to remove its inner suspension shape water droplet through the steam after the condensation process.
In waste gas treatment method of nuclear power plant of the present invention, described steps A also further comprises:
A3, heating remove steam: the gas after carbonated drink is separated feeds well heater to remove wherein remaining steam to reduce the relative humidity of waste gas;
A4, adsorption dry: residual water vapor absorption drying in the gas after steps A 3 processing is fallen.
In waste gas treatment method of nuclear power plant of the present invention, after step B, also comprise the nucleic detection alarm: detect the content of radioactive nuclide in the gas after activated charcoal is detained the bed processing, and when radionuclide amount exceeds standard, send warning.
In order to solve the problems of the technologies described above, the present invention also provide a kind of simple in structure, volume is less, processing is convenient, be difficult for to reveal gas, dangerous little nuclear power station emission-control equipment, comprise the refrigeratory and the steam-water separator that connect successively, it is characterized in that, comprise that also the activated charcoal that is placed at least one delay tank that links to each other with steam-water separator is detained bed.
In nuclear power station emission-control equipment of the present invention, comprise that also being connected in steam-water separator and activated charcoal successively is detained the well heater between the bed and is equipped with activated charcoal and/or drying agent guard bed.
In nuclear power station emission-control equipment of the present invention, also comprise the surge tank that is arranged on the refrigeratory front and links to each other with refrigeratory.
In nuclear power station emission-control equipment of the present invention, also comprise with described activated charcoal and be detained the nucleic detection alarm device that bed links to each other.
In nuclear power station emission-control equipment of the present invention, also comprise the toxic emission valve that links to each other with described nucleic detection alarm device.
Implement waste gas treatment method of nuclear power plant of the present invention and device, have following beneficial effect: it is detained bed by the activated charcoal that is placed at least one delay tank, make that the waste gas that is anhydrated circulates in activated charcoal, the dynamic absorption by activated charcoal makes in the waste gas nucleic hold-up time in delay tank elongated, thereby in certain decay period, decaying, and then harmfulness that can place to go waste gas is to emit.And the present invention comes ccontaining activated charcoal to be detained the use amount that bed can reduce delay tank with delay tank, reduces the volume of device, and whole emission-control equipment is simple in structure, processing procedure convenient, waste gas is difficult for revealing, harm reduces.
Description of drawings
The invention will be further described below in conjunction with drawings and Examples, in the accompanying drawing:
Fig. 1 is a structural representation of nuclear power station emission-control equipment in the prior art;
Fig. 2 is the structural representation of a preferred embodiment of nuclear power station emission-control equipment of the present invention;
Fig. 3 is the processing flow chart of a preferred embodiment of waste gas treatment method of nuclear power plant of the present invention.
Embodiment
The present invention makes the dynamic absorption by activated charcoal in delay tank of nuclear power station waste gas by ccontaining at least one activated charcoal in the delay tank is detained bed, make the nucleic hold-up time elongated, thereby radiation hazard is removed in decay within it.
Emission-control equipment of the present invention comprises that the refrigeratory, the steam-water separator that connect successively, the activated charcoal that is placed at least one delay tank are detained bed.
Referring to Fig. 2, it is for the structural representation of emission-control equipment preferred embodiment of the present invention.Before refrigeratory 2, be connected with and be used for the gas in the waste gas is carried out pressure balanced surge tank 1.Be connected with steam-water separator 3, well heater 4 behind the refrigeratory 2 in turn, guard bed 5, activated charcoal is detained bed 6, nucleic detection alarm device 7, toxic emission valve 8.Refrigeratory 2 is mainly used in removes the steam condensation in the waste gas, and the water droplet that steam-water separator 3 suspends in will the waste gas after condenser is handled separates, and the gas heating after 4 pairs of carbonated drinks of well heater are separated is to reduce its relative humidity.Preferably, guard bed 5 employings are built-in with the delay tank of activated charcoal and/or drying agent further the water adsorption dry in the waste gas is fallen.
In conjunction with Fig. 3, it is the exhaust-gas treatment flow process figure of the preferred embodiment of the present invention again.Waste gas separates, heats and anhydrate, reach adsorption dry to remove the water in the waste gas, to reduce the relative humidity of waste gas by compensator or trimmer pressure balance, condensation, carbonated drink successively earlier.Because the relative humidity of waste gas is low more, the performance of activated charcoal is good more.Waste gas after will anhydrating again is detained bed by activated charcoal makes it be detained decay.
Specific implementation process of the present invention is as follows: waste gas is fed surge tank 1 carry out the pressure buffer balance, surge tank 1 helps activated charcoal and is detained the stable of bed 6 interior stream pressures, also can play hydrophobic effect simultaneously.Can also in system, feed nitrogen, keep pressure-fired, enter system, also help gas flow in the system to prevent outside air.The present invention saves compressor in the prior art, and it utilizes the chilled water of nuclear power station for refrigeratory 2 steam in the waste gas to be condensed into liquid to remove, and so both can make full use of existing resource, can also reduce electricity consumption.The steam-water separator 3 in refrigeratory 2 downstreams is removed the water droplet that suspends in the waste gas.Well heater 4 is set steam also residual in the waste gas is heated to reduce the relative humidity of waste gas behind the steam-water separator 3, the relative humidity of electric heater 4 control waste gas is beneficial to downstream activated charcoal delay bed 6 and is detained radioactive nuclide better.Preferably, its relative humidity is less than 25%.With a delay tank transformation as activated charcoal and/or drying agent being set on guard bed 5, guard bed 5 to advance with the step residual steam adsorption dry is fallen.Adopt one or more delay tanks to be detained bed 6 again with ccontaining activated charcoal.The quantity of the activated charcoal delay bed 6 in each delay tank and the carbon amount of activated charcoal are relevant with the content of nucleic in exhaust gas flow and the waste gas, waste gas is dynamically adsorbed by activated charcoal in activated charcoal is detained bed 6, prolong the hold-up time of radioactive nuclide (for example iodine, uranium, xenon, krypton etc.) in delay tank, radioactive nuclide is decayed, thereafter, the waste gas after the decay just can emit.Preferably, adopt 4 18m
3The ccontaining activated charcoal of delay tank is detained bed 6 and gets final product.Like this, guarantee radgas be detained decay fully and remove dangerous in, both can reduce the use of delay tank, but conserve space and cost again.After activated charcoal is detained bed 6, nucleic detection alarm device 7 is set, it detects the content of nucleic in being detained the waste gas after decaying by for example nucleic detector, when its content meets national standard, open discharging waste gas with the toxic emission valve 8 that nucleic detection alarm device 7 links to each other, when detecting the content overproof of nucleic, nucleic detection alarm device 7 sends warning.For example, can also behind well heater 4, set up the relative humidity monitor, simultaneously, on the toxic emission pipeline, radiation monitor is set.
Nuclear power station emission-control equipment provided by the invention is particularly useful for hydrogeneous waste gas, for containing oxygen waste gas, can be directly be connected to the upstream of the electric heater of nuclear auxiliary building ventilating system and iodine adsorber to be removed with containing the female pipe of oxygen waste gas.Like this, can utilize equipment in the ready-made ventilating system of nuclear power station, not remove and contain oxygen waste gas and do not need to add again instrument and equipment, thereby, the nuclear power station emission-control equipment is simplified greatly, and can be reduced the volume of whole device, reduce and take up an area of the space, and can reduce power consumption.
Device provided by the invention all is detained bed 6 by activated charcoal at normal temperatures and pressures and removes radioactive nuclide in the waste gas, the addition of activated charcoal was determined by waste gas hold-up time and gas flow, and keep the chain of toxic emission monitoring alarm and toxic emission valve 8, in case when the warning of radioactive emission height takes place, close toxic emission valve 8.Therefore, the present invention has significantly reduced the danger that waste gas is revealed at normal temperatures and pressures.And emission-control equipment provided by the invention makes equipment take up an area of that volume reduces greatly, control and treatment is simple and convenient, the plant consumption amount reduces, technological process is simplified greatly.
The above only is the preferred embodiments of the present invention; be not so limit claim of the present invention; every equivalent structure or equivalent flow process conversion that utilizes instructions of the present invention and accompanying drawing content to be done; or directly or indirectly be used in other relevant technical fields, all in like manner be included in the scope of patent protection of the present invention.
Claims (10)
1. waste gas treatment method of nuclear power plant is characterized in that, may further comprise the steps:
A, anhydrate: remove the steam in the waste gas;
B, delay decay radioactive nuclide: the waste gas after will anhydrating is detained bed to be detained the radioactive nuclide that decays by activated charcoal.
2. waste gas treatment method of nuclear power plant according to claim 1 is characterized in that, also comprises buffering cushioning balance pressure before the described steps A: nuclear power station waste gas is fed in the surge tank carry out the stream pressure balance.
3. waste gas treatment method of nuclear power plant according to claim 1 and 2 is characterized in that, described steps A comprises:
A1, condensing water vapor: waste gas is fed refrigeratory carry out condensation and make steam be condensed into liquid;
A2, carbonated drink are separated: will feed steam-water separator to remove its inner suspension water droplet through the steam after the condensation process.
4. waste gas treatment method of nuclear power plant according to claim 3 is characterized in that, described steps A also further comprises:
A3, heating remove steam: the gas after carbonated drink is separated feeds well heater to remove wherein remaining steam to reduce the relative humidity of waste gas;
A4, adsorption dry: residual water vapor absorption drying in the gas after steps A 3 processing is fallen.
5. waste gas treatment method of nuclear power plant according to claim 1, it is characterized in that, after step B, also comprise the nucleic detection alarm: detect the content of radioactive nuclide in the gas after activated charcoal is detained the bed processing, and when radionuclide amount exceeds standard, send warning.
6. a nuclear power station emission-control equipment comprises the refrigeratory and the steam-water separator that connect successively, it is characterized in that, comprises that also the activated charcoal that is placed at least one delay tank that links to each other with steam-water separator is detained bed.
7. emission-control equipment according to claim 6 is characterized in that, comprises that also being connected in steam-water separator and activated charcoal successively is detained the well heater between the bed and is equipped with activated charcoal and/or drying agent guard bed.
8. emission-control equipment according to claim 6 is characterized in that, also comprises the surge tank that is arranged on the refrigeratory front and links to each other with refrigeratory.
9. emission-control equipment according to claim 6 is characterized in that, also comprises with described activated charcoal being detained the nucleic detection alarm device that bed links to each other.
10. emission-control equipment according to claim 9 is characterized in that, also comprises the toxic emission valve that links to each other with described nucleic detection alarm device.
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| CN200910108272A CN101847456A (en) | 2009-06-24 | 2009-06-24 | Waste gas treatment method of nuclear power plant and treatment device thereof |
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| CN200910108272A CN101847456A (en) | 2009-06-24 | 2009-06-24 | Waste gas treatment method of nuclear power plant and treatment device thereof |
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Cited By (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102226949A (en) * | 2011-04-20 | 2011-10-26 | 衡阳师范学院 | Method and device for carrying out adsorption quantity improvement and dehydrogenation on radioactive gases |
| CN103474121A (en) * | 2013-09-24 | 2013-12-25 | 中广核工程有限公司 | Radioactive waste gas treatment system for nuclear power plant |
| 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 |
| CN104575650A (en) * | 2015-01-26 | 2015-04-29 | 中国工程物理研究院核物理与化学研究所 | Radioactive iodine-131 steam treatment set |
| 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 |
| CN107093483A (en) * | 2017-04-27 | 2017-08-25 | 华北电力大学 | A kind of radionuclide collection device |
| CN107327985A (en) * | 2017-07-11 | 2017-11-07 | 上海九谷智能科技有限公司 | A kind of air fast purification system for being applicable radioactivity computer room |
| CN109712738A (en) * | 2019-01-31 | 2019-05-03 | 中国船舶重工集团公司第七一九研究所 | The Spent Radioactive gas processing system of marine floating nuclear power platform |
| 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 |
| CN110846673A (en) * | 2019-12-11 | 2020-02-28 | 陈静玲 | Multifunctional hydrogen production system for cracking methanol and water by boiling, spraying and rotary shaving paddle |
| 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 |
| CN114883022A (en) * | 2022-05-12 | 2022-08-09 | 华能核能技术研究院有限公司 | High-temperature reactor purification and regeneration waste gas treatment system and method |
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2009
- 2009-06-24 CN CN200910108272A patent/CN101847456A/en active Pending
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102226949B (en) * | 2011-04-20 | 2014-03-19 | 衡阳师范学院 | Method and device for carrying out adsorption quantity improvement and dehydrogenation on radioactive gases |
| CN102226949A (en) * | 2011-04-20 | 2011-10-26 | 衡阳师范学院 | Method and device for carrying out adsorption quantity improvement and dehydrogenation on radioactive gases |
| CN103474121A (en) * | 2013-09-24 | 2013-12-25 | 中广核工程有限公司 | Radioactive waste gas treatment system for nuclear power plant |
| 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 |
| 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 |
| CN105575452B (en) * | 2014-10-13 | 2019-08-30 | 中国辐射防护研究院 | Radioactivity inert gas gaseous-waste holdup system silica dehydrator unit desiccant application method |
| 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 |
| CN104575650A (en) * | 2015-01-26 | 2015-04-29 | 中国工程物理研究院核物理与化学研究所 | Radioactive iodine-131 steam treatment set |
| CN104575650B (en) * | 2015-01-26 | 2017-03-29 | 中国工程物理研究院核物理与化学研究所 | Radioactivity iodine 131 evaporation processing equipment |
| 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 |
| CN107093483A (en) * | 2017-04-27 | 2017-08-25 | 华北电力大学 | A kind of radionuclide collection device |
| CN107093483B (en) * | 2017-04-27 | 2024-04-09 | 华北电力大学 | Radionuclide collection device |
| CN107327985A (en) * | 2017-07-11 | 2017-11-07 | 上海九谷智能科技有限公司 | A kind of air fast purification system for being applicable radioactivity computer room |
| 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 |
| CN109712738A (en) * | 2019-01-31 | 2019-05-03 | 中国船舶重工集团公司第七一九研究所 | The Spent Radioactive gas processing system of marine floating nuclear power platform |
| CN110846673A (en) * | 2019-12-11 | 2020-02-28 | 陈静玲 | Multifunctional hydrogen production system for cracking methanol and water by boiling, spraying and rotary shaving paddle |
| 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 |
| CN114883022A (en) * | 2022-05-12 | 2022-08-09 | 华能核能技术研究院有限公司 | High-temperature reactor purification and regeneration waste gas treatment system and method |
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Application publication date: 20100929 |