CN107945898B - Integrated dry-type radioactive aerosol filtering device - Google Patents
Integrated dry-type radioactive aerosol filtering device Download PDFInfo
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- CN107945898B CN107945898B CN201711272638.0A CN201711272638A CN107945898B CN 107945898 B CN107945898 B CN 107945898B CN 201711272638 A CN201711272638 A CN 201711272638A CN 107945898 B CN107945898 B CN 107945898B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/02—Treating gases
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01D—SEPARATION
- B01D46/00—Filters or filtering processes specially modified for separating dispersed particles from gases or vapours
- B01D46/56—Filters or filtering processes specially modified for separating dispersed particles from gases or vapours with multiple filtering elements, characterised by their mutual disposition
- B01D46/62—Filters or filtering processes specially modified for separating dispersed particles from gases or vapours with multiple filtering elements, characterised by their mutual disposition connected in series
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01D—SEPARATION
- B01D53/00—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols
- B01D53/34—Chemical or biological purification of waste gases
- B01D53/74—General processes for purification of waste gases; Apparatus or devices specially adapted therefor
- B01D53/81—Solid phase processes
- B01D53/82—Solid phase processes with stationary reactants
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Abstract
The invention relates to an integrated dry-type radioactive aerosol filtering device which comprises a central cavity 1, a metal fiber filter 2, an interface section 3, an expansion section 4, a silver zeolite filter 5, a contraction section 6, a rupture membrane 7, an outlet pipe 8, a pressure-bearing shell 9, an inlet 10, an end cavity 11, a condensate discharge pipe 12, a heat exchange pipe 13, a metal fiber filter liquid drainage pipe 14, a throttling and pressure reducing pore plate 15 and a flow equalizing pore plate 16; the metal fiber filter 2 completes the dehumidification and dust removal process of the filtered mixed gas, and the silver zeolite filter 5 removes radioactive iodine in the filtered mixed gas through chemical reaction. The invention adopts an integrated structure, has high operation pressure, can effectively reduce the volume of the silver zeolite filter 5 and reduce the production cost of equipment. The invention adopts the passive design of the rupture disk 7, and has simple structure, safe operation and high reliability. The invention has simple integral structure, small volume and good economical efficiency, and can be conveniently arranged, installed and maintained.
Description
Technical Field
The invention belongs to the technical field of nuclear reactor safety, and particularly relates to an integrated dry radioactive aerosol filtering device.
Background
The nuclear power plant containment is the last barrier to prevent the release of radioactive products into the environment, and its integrity plays an important role in environmental protection. The containment filtering and discharging system ensures the integrity of the containment by actively releasing pressure and discharging so that the pressure in the containment does not exceed the bearing limit value of the containment, and meanwhile, the filtering device arranged on the pressure releasing pipeline filters radioactive substances in the discharged gas so as to prevent the radioactive substances from causing serious harm to the environment. Foreign research on containment filtered venting devices, such as sand bed filtered venting systems, wet filters, etc., is initiated early. The research in this aspect in China starts late, and as seen from documents such as experimental research on aerosol removal characteristics of a venturi scrubber, reported in the fourteenth national nuclear reactor thermotechnical fluid academic conference paper, experimental research on gaseous methyl iodide removal characteristics, reported in volume 47, volume 11 of atomic energy science and technology, and the like, the filtration efficiency of the venturi filter on aerosol and iodine after a serious water washing accident is very high, but the filtration efficiency on radioactive methyl iodide cannot meet the requirement of a safe emission index, and methyl iodide cannot be effectively removed only by means of a prepared water washing chemical solution. In order to effectively remove the radioactive methyl iodide, the silver-loaded zeolite can be used as an adsorbing material and applied to a filtering and discharging system. The silver-carrying zeolite is used as an adsorbent and has been applied to the field of chemical engineering.
Patent CN100509138C proposes the use of silver-carrying acid-resistant zeolite to adsorb and remove trace iodide in acetic anhydride product. The method has high adsorption effect on iodide molecules with different sizes, can effectively remove inorganic and/or organic iodides and/or molecular iodine in the acetic anhydride crude product, and has the removal efficiency of more than 99%. Patent CN106554272A proposes that iodine ions in organic acid can be removed by using silver zeolite, and a silver-loaded molecular sieve prepared by vacuum impregnation method is used as an adsorbent, so that organic acid can pass through the adsorbent at a certain speed, iodine ions can be effectively removed, and silver ions are not easy to fall off. The radionuclide iodine-131 in the gas can be removed by chemical reaction using silver zeolite, but its filtration efficiency is greatly affected by humidity due to its inherent hydrophilicity. Therefore, how to improve the efficiency of removing methyl iodide from silver zeolite at the initial stage of starting a filtering and discharging system is one of the technical problems to be solved in the international standards at present.
The improvement of the efficiency of the silver zeolite in removing methyl iodide requires the following conditions that steam is in a superheated state; the flow rate of the mixed gas is low; the silver zeolite filtering layer has large thickness; the equipment is preheated before starting.
Disclosure of Invention
Aiming at the defects in the prior art, the invention aims to provide an integrated dry radioactive aerosol filtering device which is simple in structure and safe in operation.
The purpose of the invention is realized as follows:
the invention relates to an integrated dry-type radioactive aerosol filtering device which comprises a central cavity 1, a metal fiber filter 2, an interface section 3, an expansion section 4, a silver zeolite filter 5, a contraction section 6, a rupture membrane 7, an outlet pipe 8, a pressure-bearing shell 9, an inlet 10, an end cavity 11, a condensate discharge pipe 12, a heat exchange pipe 13, a metal fiber filter liquid drainage pipe 14, a throttling and pressure reducing pore plate 15 and a flow equalizing pore plate 16; the method is characterized in that: the pressure-bearing shell 9 is symmetrical in internal structure, the inlets 10 are arranged at two ends of the pressure-bearing shell 9, the metal fiber filter 2 is arranged in the middle, the silver zeolite filters 5 are arranged at two ends of the pressure-bearing shell 9, and the heat exchange tubes 13 are arranged in the silver zeolite filters 5; the metal fiber filter 2 and the silver zeolite filter 5 are connected by an interface section 3 and an expansion section 4; the outer wall of the silver zeolite filter 5 is welded with the inner wall of the pressure-bearing shell 9, and the pressure-bearing shell 9 is divided into a central chamber 1 and an end chamber 11; the outlet pipe 8 is arranged in the end chamber 11, the outlet pipe 8 is provided with a rupture disk 7, and the outlet pipe 8 is connected with the silver zeolite filter 5 through the contraction section 6; the bottom of the central chamber 1 and the bottom of the end chamber 11 are respectively provided with a condensate discharge pipe 12; the metal fiber filter 2 comprises a pre-filtering layer and a fine filtering layer, and the pre-filtering layer is connected with a metal fiber filter liquid dredging pipe 14; a condensate discharge pipe 12 and a metal fiber filter drain pipe 14 penetrate through the bottom of the pressure-bearing shell 9.
And the interface section 3 and the expansion section 4 are respectively provided with a throttling pressure-reducing orifice plate 15 and a flow-equalizing orifice plate 16.
The silver zeolite filter 5 adopts a heat exchanger structure, and radioactive nuclide iodine-131 is removed through chemical reaction of silver and iodine; the heat exchange pipe 13 is in a cross arrangement structure.
The heat exchange tube 13 has a slight inclination.
The thickness of the silver zeolite filter 5 is not less than 5 cm.
Compared with the prior art, the invention has the beneficial effects that:
the invention adopts the silver zeolite adsorption method, effectively removes radioactive substances in the gas, and the heat exchange tube 13 can effectively preheat and continuously heat the silver zeolite filter 5, thereby improving the operation reliability of the device.
The silver zeolite filter 5 designed by the invention can effectively remove iodine-131 contained in radioactive gas, so that the filtered gas reaches the environmental emission standard.
The throttling and pressure reducing orifice plate 15 in the invention ensures that steam in the mixed gas to be filtered is in an overheated state, and the expansion section 4 with the flow equalizing orifice plate 16 is adopted to ensure that the flow is uniformly distributed while the gas is subjected to speed reduction, thereby avoiding the problem of low local removal efficiency caused by overhigh local flow velocity.
The invention adopts an integrated arrangement structure, which can effectively reduce the volume of the silver zeolite filter 5 and reduce the production cost;
the rupture disk 7 can be automatically opened, and has safe operation and high reliability.
The invention has simple integral structure, small volume and good economical efficiency, and can be conveniently arranged, installed and maintained.
Drawings
Fig. 1 is a schematic view of the overall structure of the present invention.
Detailed Description
The invention will be described in more detail below with reference to the following detailed description and the accompanying drawings:
with reference to fig. 1, the integrated dry-type radioactive aerosol filtering device provided by the invention mainly comprises a central cavity 1, a metal fiber filter 2, an interface section 3, an expansion section 4, a silver zeolite filter 5, a contraction section 6, a rupture membrane 7, an outlet pipe 8, a pressure-bearing shell 9, an inlet 10, an end cavity 11, a condensate discharge pipe 12, a heat exchange pipe 13, a metal fiber filter liquid dredging pipe 14, a throttling and pressure reducing pore plate 15 and a flow equalizing pore plate 16.
Atmospheric nitrogen is initially filled in the pressure-bearing shell 9. The outlet of the outlet pipe 8 is controlled by the rupture disk 7 in its opening pressure. Under the action of pressure difference, high-temperature and high-pressure mixed gas to be filtered enters an end cavity 11 from inlets 10 at two ends at the initial stage, then enters a central cavity 1 through a heat exchange pipe 13, a silver zeolite filter 5 and a metal fiber filter 2 are preheated through surface convection heat exchange, steam in the mixed gas is condensed to release heat, and condensate is discharged out of a pressure-bearing shell 9 through a condensate discharge pipe 12. The pressure in the pressure-bearing shell 9 is gradually increased along with the continuous entering of the gas to be filtered into the pressure-bearing shell 9, when the pressure in the pressure-bearing shell 9 exceeds the set pressure (0.5MPa) of the rupture membrane 7 on the downstream pipeline, the rupture membrane 7 is opened, the preheating working condition is finished, and the filtering and discharging working condition is started.
The gas to be filtered firstly enters the metal fiber filter 2 and flows out from the interface sections 3 at two sides, the metal fiber filter 2 adopts a mode of two-stage series connection of a pre-filtering layer and a fine filtering layer, a large amount of micron-sized small drops and aerosol particles carried in the mixed gas are removed through the pre-filtering layer, and the aerosol with smaller particle size is further removed through the fine filtering layer. The filtered impurities are discharged through the metal fiber filter liquid discharge pipe 14.
The dry vapor containing radioactive iodine enters the silver zeolite filter 5 through the mouthpiece section 3 and the expansion section 4. A pressure reduction orifice plate 15 is arranged in the interface section 3, so that steam in the mixed gas is in a superheated state. The jet flow flowing out of the pressure-reducing orifice plate 15 enters the expansion section 4, and the flow velocity is reduced due to the expansion of the flow cross section. The expansion section 4 is internally provided with a secondary flow equalizing pore plate 16, so that the flow velocity of each part in the flow cross section is basically equal when the fluid enters the silver zeolite filter 5. The area of the flow cross section in the silver zeolite filter 5 is larger than that of the expansion section 4, so that the flow speed is further reduced, the radioactive substance iodine in the mixed gas is fully contacted with the silver zeolite, and the radioactive iodine is removed through chemical reaction. The cleaned gas then enters the constriction 6 and is finally discharged through the outlet duct 8.
The silver zeolite filter 5 adopts a structure form of a heat exchanger, a crossed heat exchange pipe 13 is arranged in the filter, and silver zeolite is filled between the outside of the heat exchange pipe 13 and the shell of the silver zeolite filter 5. The filtered mixed gas can continuously heat the silver zeolite in the flowing process, so that the silver zeolite is always in a heated state in the whole operation process, preheating can be realized on the one hand, and the problem of low radioactive iodine removal efficiency of the silver zeolite caused by partial steam condensation is also relieved on the other hand.
The thickness of the silver zeolite filtering layer in the silver zeolite filter 5 is not less than 5cm, and based on the space requirement of equipment, the thickness of the filtering layer can be properly increased, the contact time of the radioactive mixed gas and the silver zeolite is prolonged, and the filtering efficiency is improved.
It will be appreciated by those of ordinary skill in the art that the embodiments described herein are intended to assist the reader in understanding the principles of the invention and are to be construed as being without limitation to such specifically recited embodiments and examples. All such possible equivalents and modifications are deemed to fall within the scope of the invention as defined in the claims.
Claims (5)
1. An integrated dry radioactive aerosol filtering device comprises a central cavity (1), a metal fiber filter (2), an interface section (3), an expansion section (4), a silver zeolite filter (5), a contraction section (6), a rupture membrane (7), an outlet pipe (8), a pressure-bearing shell (9), an inlet (10), an end cavity (11), a condensate discharge pipe (12), a heat exchange pipe (13), a metal fiber filter liquid dredging pipe (14), a throttling and pressure reducing pore plate (15) and a flow equalizing pore plate (16); the method is characterized in that: the pressure-bearing shell (9) is symmetrical in internal structure, inlets (10) are arranged at two ends of the pressure-bearing shell (9), the metal fiber filter (2) is arranged in the middle, the silver zeolite filter (5) is arranged at two ends of the pressure-bearing shell (9), and heat exchange tubes (13) are arranged in the silver zeolite filter (5); the metal fiber filter (2) and the silver zeolite filter (5) are connected by an interface section (3) and an expansion section (4); the outer wall of the silver zeolite filter (5) is welded with the inner wall of the pressure-bearing shell (9) to divide the interior of the pressure-bearing shell (9) into a central chamber (1) and an end chamber (11); the outlet pipe (8) is arranged in the end chamber (11), the outlet pipe (8) is provided with a rupture disk (7), and the outlet pipe (8) is connected with the silver zeolite filter (5) through the contraction section (6); the bottoms of the central chamber (1) and the end chamber (11) are respectively provided with a condensate discharge pipe (12); the metal fiber filter (2) comprises a pre-filtering layer and a fine filtering layer, and the pre-filtering layer is connected with a drain pipe (14) of the metal fiber filter; the condensate discharge pipe (12) and the metal fiber filter drain pipe (14) penetrate through the bottom of the pressure-bearing shell (9).
2. An integrated dry radioactive aerosol filtration device according to claim 1, wherein: the interface section (3) is provided with a throttling pressure reducing orifice plate (15), and the expansion section (4) is provided with a flow equalizing orifice plate (16).
3. An integrated dry radioactive aerosol filtration device according to claim 1, wherein: the silver zeolite filter (5) removes radionuclide iodine-131 through chemical reaction of silver and iodine; the heat exchange tubes (13) are in a cross arrangement structure.
4. An integrated dry radioactive aerosol filtration device according to claim 1, wherein: the heat exchange tube (13) has a slight inclination.
5. An integrated dry radioactive aerosol filtration device according to claim 1, wherein: the thickness of the silver zeolite filter (5) is not less than 5 cm.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201711272638.0A CN107945898B (en) | 2017-12-06 | 2017-12-06 | Integrated dry-type radioactive aerosol filtering device |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201711272638.0A CN107945898B (en) | 2017-12-06 | 2017-12-06 | Integrated dry-type radioactive aerosol filtering device |
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| CN107945898A CN107945898A (en) | 2018-04-20 |
| CN107945898B true CN107945898B (en) | 2020-05-15 |
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| CN201711272638.0A Active CN107945898B (en) | 2017-12-06 | 2017-12-06 | Integrated dry-type radioactive aerosol filtering device |
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Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108801715B (en) * | 2018-05-18 | 2024-05-28 | 南京航空航天大学 | Measuring method of radioactive aerosol real-time sampling measuring device |
| CN113720659A (en) * | 2021-08-25 | 2021-11-30 | 哈尔滨工程大学 | Gas sampling and filtering device for monitoring hydrogen concentration in containment vessel under severe accident of nuclear power plant |
| CN113952845B (en) * | 2021-11-05 | 2022-07-15 | 岭东核电有限公司 | Membrane filter material, preparation method thereof and application of membrane filter material in treating aerosol |
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| CN106716547A (en) * | 2014-07-14 | 2017-05-24 | 阿拉法股份有限公司 | Convective dry filtered containment venting system |
| CN205448055U (en) * | 2016-03-14 | 2016-08-10 | 西安交通大学 | Photocatalytic air purification ware that contains drainage formula water bath unit |
| CN106384607A (en) * | 2016-10-08 | 2017-02-08 | 哈尔滨工程大学 | Containment filtering and discharging system capable of carrying out passive operation for a long term |
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