CN112473340A - Nuclear power plant containment filtering and discharging system - Google Patents
Nuclear power plant containment filtering and discharging system Download PDFInfo
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- CN112473340A CN112473340A CN202011245756.4A CN202011245756A CN112473340A CN 112473340 A CN112473340 A CN 112473340A CN 202011245756 A CN202011245756 A CN 202011245756A CN 112473340 A CN112473340 A CN 112473340A
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- 238000001914 filtration Methods 0.000 title claims abstract description 92
- 238000007599 discharging Methods 0.000 title claims abstract description 23
- INQOMBQAUSQDDS-UHFFFAOYSA-N iodomethane Chemical compound IC INQOMBQAUSQDDS-UHFFFAOYSA-N 0.000 claims abstract description 37
- 238000005406 washing Methods 0.000 claims abstract description 34
- 229910052709 silver Inorganic materials 0.000 claims abstract description 26
- 239000004332 silver Substances 0.000 claims abstract description 26
- BQCADISMDOOEFD-UHFFFAOYSA-N Silver Chemical compound [Ag] BQCADISMDOOEFD-UHFFFAOYSA-N 0.000 claims abstract description 22
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 claims abstract description 19
- 239000001257 hydrogen Substances 0.000 claims abstract description 18
- 229910052739 hydrogen Inorganic materials 0.000 claims abstract description 18
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 17
- 229910021536 Zeolite Inorganic materials 0.000 claims abstract description 16
- HNPSIPDUKPIQMN-UHFFFAOYSA-N dioxosilane;oxo(oxoalumanyloxy)alumane Chemical compound O=[Si]=O.O=[Al]O[Al]=O HNPSIPDUKPIQMN-UHFFFAOYSA-N 0.000 claims abstract description 16
- 239000010457 zeolite Substances 0.000 claims abstract description 16
- 230000000149 penetrating effect Effects 0.000 claims abstract description 12
- 230000002285 radioactive effect Effects 0.000 claims abstract description 9
- 230000008030 elimination Effects 0.000 claims abstract description 7
- 238000003379 elimination reaction Methods 0.000 claims abstract description 7
- 239000003638 chemical reducing agent Substances 0.000 claims abstract description 4
- 239000012528 membrane Substances 0.000 claims abstract description 4
- 230000035515 penetration Effects 0.000 claims abstract description 4
- 238000002955 isolation Methods 0.000 claims description 6
- 239000002245 particle Substances 0.000 claims description 6
- 239000007788 liquid Substances 0.000 claims description 4
- 239000000126 substance Substances 0.000 claims description 4
- 238000006356 dehydrogenation reaction Methods 0.000 claims description 3
- 238000005070 sampling Methods 0.000 claims description 3
- 238000013022 venting Methods 0.000 claims 5
- 230000009977 dual effect Effects 0.000 claims 1
- 238000004880 explosion Methods 0.000 abstract description 7
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 description 7
- 239000007789 gas Substances 0.000 description 7
- 229910052740 iodine Inorganic materials 0.000 description 7
- 239000011630 iodine Substances 0.000 description 7
- 239000000443 aerosol Substances 0.000 description 5
- -1 Silver ions Chemical class 0.000 description 4
- 239000000835 fiber Substances 0.000 description 4
- 229910052751 metal Inorganic materials 0.000 description 4
- 239000002184 metal Substances 0.000 description 4
- 239000000941 radioactive substance Substances 0.000 description 4
- 238000001179 sorption measurement Methods 0.000 description 4
- OKKJLVBELUTLKV-UHFFFAOYSA-N Methanol Chemical compound OC OKKJLVBELUTLKV-UHFFFAOYSA-N 0.000 description 2
- 238000009825 accumulation Methods 0.000 description 2
- 239000000428 dust Substances 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- PNDPGZBMCMUPRI-UHFFFAOYSA-N iodine Chemical compound II PNDPGZBMCMUPRI-UHFFFAOYSA-N 0.000 description 2
- 239000011148 porous material Substances 0.000 description 2
- 230000000717 retained effect Effects 0.000 description 2
- 239000002699 waste material Substances 0.000 description 2
- 238000010521 absorption reaction Methods 0.000 description 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 230000033228 biological regulation Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 230000002209 hydrophobic effect Effects 0.000 description 1
- 238000001802 infusion Methods 0.000 description 1
- 230000014759 maintenance of location Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 238000011045 prefiltration Methods 0.000 description 1
- 239000012798 spherical particle Substances 0.000 description 1
- 230000001502 supplementing effect Effects 0.000 description 1
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01D—SEPARATION
- B01D53/00—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols
- B01D53/34—Chemical or biological purification of waste gases
- B01D53/74—General processes for purification of waste gases; Apparatus or devices specially adapted therefor
- B01D53/75—Multi-step processes
-
- 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
- B01D53/14—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols by absorption
- B01D53/1487—Removing organic compounds
-
- 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
- B01D53/14—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols by absorption
- B01D53/18—Absorbing units; Liquid distributors therefor
-
- 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
- B01D53/46—Removing components of defined structure
- B01D53/68—Halogens or halogen compounds
- B01D53/70—Organic halogen compounds
-
- 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
-
- 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
- B01D53/86—Catalytic processes
- B01D53/8659—Removing halogens or halogen compounds
- B01D53/8662—Organic halogen compounds
-
- 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
- B01D53/86—Catalytic processes
- B01D53/8671—Removing components of defined structure not provided for in B01D53/8603 - B01D53/8668
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/28—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
- G21C19/30—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps
- G21C19/303—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps specially adapted for gases
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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
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01D—SEPARATION
- B01D2257/00—Components to be removed
- B01D2257/20—Halogens or halogen compounds
- B01D2257/206—Organic halogen compounds
- B01D2257/2068—Iodine
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Plasma & Fusion (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention discloses a containment filtering and discharging system of a nuclear power plant, which comprises: a containment penetration assembly penetrating the containment; the washing filtering device is connected into the containment through a pipeline penetrating through the containment penetrating piece assembly and is provided with a hydrogen elimination device; the AgX type methyl iodide filtering device and the AgR type methyl iodide filtering device are arranged in parallel at the downstream of the water washing filtering device; and a pressure balance valve, a safety valve, a flow-limiting orifice plate, a rupture membrane, a reducer, a radioactive dose monitor and a chimney which are sequentially arranged at the downstream of the AgX type methyl iodide filtering device and the AgR type methyl iodide filtering device. Compared with the prior art, the containment filtration and discharge system of the nuclear power plant is provided with the AgX type silver zeolite hydrogen elimination device in the containment washing and filtration device, and the AgX type methyl iodide filtration device and the AgR type methyl iodide filtration device are arranged at the downstream, so that the problems of hydrogen explosion risk and low methyl iodide removal efficiency when the containment filtration and discharge system is required to be put into operation after a serious accident are fundamentally solved.
Description
Technical Field
The invention belongs to the technical field of nuclear power, and particularly relates to a containment filtering and discharging system of a nuclear power plant.
Background
According to the requirements of IAEA guide rule NS-G-1.10 and HAF102 design safety regulation of nuclear power plant: the design must be such as to practically eliminate the possibility of nuclear power plant conditions that may lead to early radioactive emissions or significant radioactive emissions. After a severe accident occurs to a nuclear power plant reactor, the melting of the reactor core causes a large amount of steam and non-condensable gas to be continuously accumulated in the containment, and the integrity of the containment is seriously threatened. Therefore, it is necessary to vent these gases out of the shell by active pressure relief so that the pressure in the containment vessel does not exceed its load limit, ensuring the integrity of the containment vessel.
In order to prevent the gas discharged out of the containment from causing unacceptable radioactive hazard consequences to the environment and the public, it is necessary to provide a filtering device on the pressure relief line to filter and retain the radioactive substances in the discharged gas, so that the radioactive substances inevitably released into the environment are maintained at the lowest possible level, and the environment-friendly and public dose safety is ensured.
According to the requirements of IAEA Safety Standards Series No. NS-G-1.10, the efficient containment filtration and discharge system is selected to eliminate the overpressure risk of the containment and avoid the uncontrollable release of radioactive substances, so that the method has practical significance. At present, most of newly built and in-service pressurized water reactor nuclear power plants at home and abroad are provided with a containment filtering and discharging system after a serious accident so as to ensure the integrity of the containment and prevent the release of large-scale radioactive substances caused by the overpressure of the containment. At present, the mainly adopted technical scheme comprises: dry filtration (adsorption filtration outside the housing) and wet filtration (combination of venturi wash filtration outside the housing and metal fiber filtration).
For dry filtration, mainly provide a pressurized water reactor nuclear power plant with the functions of containing dust and aerosol of metal fiber prefiltering in the shell, iodine adsorption filtration outside the shell, when the containment is over-pressurized after a serious accident, preliminarily filter the aerosol through the metal fiber prefilter in the shell, reduce the dust containing amount and aerosol with super large particle size of the filtered exhaust gas, adsorb and retain the radioactive particles in the exhaust gas through the dry iodine adsorption device outside the shell, execute a controlled pressure relief mode to keep the pressure in the containment not to exceed the bearing limit value thereof, and maintain the integrity of the containment. The dry filtration has certain reliability, but has high requirements on adsorption materials, the device is large in size, and stagnant substances in the filtration device are easy to decay and collect, so that equipment is burnt out and radioactivity leaks out. In addition, dry filtration also makes it difficult to avoid the risk of hydrogen explosions caused by local accumulation of hydrogen gas within the device.
For wet filtration, a passive pressurized water reactor nuclear power plant filtering, discharging and retaining device with functions of water washing, retaining and mechanical filtering is mainly provided. When the containment is in overpressure after a serious accident, elemental iodine, soluble aerosol and soluble organic iodine in exhaust gas are retained by a Venturi scrubber solution arranged outside the shell, micro aerosol particles with different sizes are retained by a second-stage metal fiber filter, a passive controlled pressure relief mode is executed to keep the pressure in the containment not to exceed the bearing limit value of the containment, and the integrity of the containment is maintained. The wet filtration has high reliability, has high retention efficiency for radionuclides except methyl iodide, and is difficult to avoid hydrogen explosion risk caused by local accumulation of hydrogen in the device.
In view of the above, there is a need to provide a containment filtration discharge system for a nuclear power plant, which can effectively reduce the risk of hydrogen explosion and improve the methyl iodide removal efficiency.
Disclosure of Invention
The invention aims to: the defects of the prior art are overcome, and the containment filtering and discharging system of the nuclear power plant, which can effectively reduce the hydrogen explosion risk and improve the methyl iodide removal efficiency, is provided.
In order to achieve the above object, the present invention provides a containment filtered discharge system of a nuclear power plant, including:
a containment penetration assembly penetrating the containment;
the washing filtering device is connected into the containment through a pipeline penetrating through the containment penetrating piece assembly and is provided with a hydrogen elimination device; and
and the AgX type methyl iodide filter device and the AgR type methyl iodide filter device are connected in parallel and arranged at the downstream of the water washing filter device.
As an improvement of the containment filtering and discharging system of the nuclear power plant, AgX type comprehensive silver zeolite in the AgX type methyl iodide filtering device is spherical, the grain diameter is 1.3-1.5mm, and the proportion of silver element is about 40%.
As an improvement of the containment filtering and discharging system of the nuclear power plant, the AgR type comprehensive silver zeolite in the AgR type methyl iodide filtering device is granular, the grain diameter is 2.9-3.1mm, and the proportion of silver element is about 10%.
As an improvement of the containment filtering and discharging system of the nuclear power plant, a double electric isolation valve assembly is arranged on a pipeline connecting the water washing filtering device to the inside of the containment.
As an improvement of the containment filtering and discharging system of the nuclear power plant, the top of the washing filtering device is provided with a baffle AgX type silver zeolite dehydrogenation device.
As an improvement of the containment filtering and discharging system of the nuclear power plant, a Venturi nozzle and a washing solution are arranged at the bottom of the washing filtering device, and an inlet and an outlet of the washing filtering device are connected with external equipment through flanges.
As an improvement of the containment filtering and discharging system of the nuclear power plant, a sampling isolation valve is arranged at the bottom of the washing filtering device.
As an improvement of the containment filtering and discharging system of the nuclear power plant, a return pipe is arranged at the bottom of the washing filtering device and is connected with a pipeline connecting the washing filtering device and the containment, and a return valve is arranged on the return pipe.
As an improvement of the containment filtering and discharging system of the nuclear power plant, the return pipe is respectively connected with the chemical liquid supplementing device and the drainage connector through quick connectors.
As an improvement of the containment filtering and discharging system of the nuclear power plant, a pressure balance valve, a safety valve, a flow-limiting pore plate, a rupture membrane, a reducer, a radioactive dose monitor and a chimney are sequentially arranged at the downstream of the AgX type methyl iodide filtering device and the AgR type methyl iodide filtering device.
Compared with the prior art, the containment filtering and discharging system of the nuclear power plant is provided with the AgX type silver zeolite hydrogen elimination device in the containment washing and filtering device, and the AgX type methyl iodide filtering device and the AgR type methyl iodide filtering device are arranged at the downstream, so that the problems of hydrogen explosion risk and low methyl iodide removal efficiency when the containment filtering and discharging system is required to be put into operation after a serious accident are fundamentally solved, and the safety and the reliability of the containment filtering and discharging system are improved.
Drawings
The following detailed description of the filtering and discharging system for containment vessel of nuclear power plant and its technical effects will be made with reference to the accompanying drawings and the detailed description, in which:
fig. 1 is a schematic structural diagram of a containment filtration and discharge system of a nuclear power plant according to the present invention.
Detailed Description
In order to make the objects, technical solutions and technical effects of the present invention more clear, the present invention is further described in detail below with reference to the accompanying drawings and the detailed description. It should be understood that the detailed description and specific examples, while indicating the preferred embodiment of the invention, are intended for purposes of illustration only and are not intended to limit the scope of the invention.
Referring to fig. 1, the present invention provides a containment filtering and discharging system of a nuclear power plant, which includes:
a containment penetration assembly 1 penetrating the containment;
the washing filtering device 3 is connected into the containment through a pipeline penetrating through the containment penetrating piece assembly 1 and is provided with a hydrogen elimination device; and
an AgX type methyl iodide filter 7 and an AgR type methyl iodide filter 8 are arranged in parallel at the downstream of the water washing filter 3.
Silver ions are well known for their remarkable ability to trap and solidify iodine. According to one embodiment of the invention, the AgX type comprehensive silver zeolite is spherical, the spherical particle size is about 1.3-1.5mm, the iodine trapping medium is silver ions in the silver zeolite, the proportion of silver element is about 40%, the AgX type comprehensive silver zeolite has strong capability of catalyzing the reaction of hydrogen and oxygen, and meanwhile, the AgX can work at a lower temperature and has strong capability of trapping methyl iodide. After absorbing iodine, AgX is not released again due to the influence of irradiation. Therefore, radioactive iodine is permanently removed by silver ions. AgX demonstrates high absorption efficiency for methyl iodide under high temperature, high pressure, high relative humidity conditions.
CH3I+H2O+Ag+→AgI+CH3OH+H+ (1)
CH3I+CH3OH+Ag+→AgI+CH3OCH3+H+ (2)
According to one embodiment of the present invention, the AgR-type integrated silver zeolite has a granular shape with an equivalent particle size of about 2.9-3.1mm, the iodine trapping medium is silver ions in the silver zeolite with a silver element proportion of about 10%, and the AgR-type silver zeolite can operate in a mixed atmosphere of high-concentration hydrogen and air (hydrogen concentration up to 10%). AgR has a stronger methyl iodide capture capacity.
As shown in fig. 1, two parallel channels are provided between the inlet pipeline and the inlet of the water washing and filtering device 3, which are a passive discharge channel and a passive waste liquid return channel. The washing filtering device is connected to a passive discharge channel in the containment, a double electric isolation valve assembly 2 is installed on the passive discharge channel, and a return valve 4 is installed on the passive waste liquid return channel. The bottom of the water washing filter device 3 is provided with a Venturi nozzle and a washing solution, and the inlet and the outlet of the water washing filter device 3 are connected with external equipment through flanges. The top of the water washing filtering device 3 is provided with a baffle plate AgX type silver zeolite dehydrogenation device 5, and a pressure balance valve 9, a safety valve 10, a flow limiting pore plate 11, a rupture membrane 12, a reducer 13, a radioactive dose monitor 14 and a chimney 15 are sequentially arranged at the downstream of an AgX type methyl iodine filtering device 7 and an AgR type methyl iodine filtering device 8.
According to one embodiment of the present invention, the bottom of the water wash filter unit 3 is provided with a sampling isolation valve (not labeled). The bottom of washing filter equipment 3 still is equipped with the back flow (not mark), and the pipeline that washing filter equipment 3 and containment were connected is connected to the back flow, is equipped with backward flow valve 4 on the back flow, and the back flow passes through quick-operation joint and connects chemical fluid infusion device and hydrophobic joint respectively.
Compared with the prior art, the containment filtration and discharge system of the nuclear power plant is provided with the AgX type silver zeolite hydrogen elimination device in the containment washing and filtration device, and the AgX type methyl iodide filtration device and the AgR type methyl iodide filtration device are arranged at the downstream, so that the problems of hydrogen explosion risk and low methyl iodide removal efficiency when the containment filtration and discharge system needs to be put into operation after a serious accident are fundamentally solved, and the safety and the reliability of the containment filtration and discharge system are improved.
The present invention can be modified and adapted appropriately from the above-described embodiments, according to the principles described above. Therefore, the present invention is not limited to the specific embodiments disclosed and described above, and some modifications and variations of the present invention should fall within the scope of the claims of the present invention. Furthermore, although specific terms are employed herein, they are used in a generic and descriptive sense only and not for purposes of limitation.
Claims (10)
1. A nuclear power plant containment filtered venting system, comprising:
a containment penetration assembly penetrating the containment;
the washing filtering device is connected into the containment through a pipeline penetrating through the containment penetrating piece assembly and is provided with a hydrogen elimination device; and
and the AgX type methyl iodide filter device and the AgR type methyl iodide filter device are connected in parallel and arranged at the downstream of the water washing filter device.
2. The nuclear power plant containment filtration and discharge system of claim 1, wherein the AgX type synthetic silver zeolite in the AgX type methyl iodide filter device is spherical, the particle size is 1.3-1.5mm, and the proportion of silver element is about 40%.
3. The nuclear power plant containment filtration discharge system of claim 1 wherein the AgR type of integrated silver zeolite in the AgR type methyl iodide filtration unit is granular with a particle size of 2.9-3.1mm and a silver element proportion of about 10%.
4. The nuclear power plant containment filtered venting system of claim 1 wherein a dual electrically-powered isolation valve assembly is provided on the conduit connecting the water wash filter to the inside of the containment.
5. The nuclear power plant containment filtration and discharge system according to claim 1, wherein a baffle AgX type silver zeolite dehydrogenation device is arranged at the top of the water washing and filtration device.
6. The nuclear power plant containment filtering and discharging system according to claim 1, wherein a venturi nozzle and a washing solution are arranged at the bottom of the washing filtering device, and an inlet and an outlet of the washing filtering device are connected with external equipment through flanges.
7. The nuclear power plant containment filtered venting system of claim 1 wherein a sampling isolation valve is provided at a bottom of the water wash filtering device.
8. The nuclear power plant containment filtering and discharging system according to claim 1, wherein a return pipe is arranged at the bottom of the washing filtering device and connected with a pipeline connecting the washing filtering device and the containment, and a return valve is arranged on the return pipe.
9. The nuclear power plant containment filtration and venting system according to claim 8, wherein the return pipe is connected to the chemical liquid replenishing device and the drain connector through quick connectors, respectively.
10. The nuclear power plant containment filtered venting system of any one of claims 1 to 9 wherein a pressure balance valve, a safety valve, a restricted orifice plate, a rupture membrane, a reducer, a radioactive dose monitor and a chimney are installed in sequence downstream of the AgX type methyl iodide filtration unit and the AgR type methyl iodide filtration unit.
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Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
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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 |
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