CN117594255A - Device for releasing pressure to seawater under severe accident of ocean floating nuclear power plant - Google Patents
Device for releasing pressure to seawater under severe accident of ocean floating nuclear power plant Download PDFInfo
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- CN117594255A CN117594255A CN202311546778.8A CN202311546778A CN117594255A CN 117594255 A CN117594255 A CN 117594255A CN 202311546778 A CN202311546778 A CN 202311546778A CN 117594255 A CN117594255 A CN 117594255A
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- 239000013535 sea water Substances 0.000 title claims abstract description 40
- 238000007599 discharging Methods 0.000 claims abstract description 84
- 238000001914 filtration Methods 0.000 claims abstract description 48
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 17
- 239000002184 metal Substances 0.000 claims abstract description 15
- 239000000835 fiber Substances 0.000 claims abstract description 11
- 238000012806 monitoring device Methods 0.000 claims description 20
- 238000004891 communication Methods 0.000 claims description 17
- 238000002955 isolation Methods 0.000 claims description 13
- 238000001514 detection method Methods 0.000 claims description 12
- 238000005406 washing Methods 0.000 claims description 7
- 238000012545 processing Methods 0.000 claims description 4
- 238000007789 sealing Methods 0.000 claims description 3
- 230000002285 radioactive effect Effects 0.000 abstract description 40
- 239000000443 aerosol Substances 0.000 abstract description 15
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 abstract description 8
- 229910052740 iodine Inorganic materials 0.000 abstract description 8
- 239000011630 iodine Substances 0.000 abstract description 8
- 239000002245 particle Substances 0.000 abstract description 8
- 230000005855 radiation Effects 0.000 abstract description 8
- PNDPGZBMCMUPRI-UHFFFAOYSA-N iodine Chemical compound II PNDPGZBMCMUPRI-UHFFFAOYSA-N 0.000 abstract description 4
- 239000007789 gas Substances 0.000 description 27
- 238000000034 method Methods 0.000 description 10
- 230000008569 process Effects 0.000 description 10
- 238000012544 monitoring process Methods 0.000 description 6
- 238000013461 design Methods 0.000 description 4
- 230000006837 decompression Effects 0.000 description 3
- 230000007613 environmental effect Effects 0.000 description 3
- 238000011156 evaluation Methods 0.000 description 3
- 238000010521 absorption reaction Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 239000000941 radioactive substance Substances 0.000 description 2
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 1
- 230000004888 barrier function Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 108010066057 cabin-1 Proteins 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000006073 displacement reaction Methods 0.000 description 1
- 238000004880 explosion Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 230000004927 fusion Effects 0.000 description 1
- 239000001257 hydrogen Substances 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
- 230000004044 response Effects 0.000 description 1
- 239000004576 sand Substances 0.000 description 1
- 230000007704 transition Effects 0.000 description 1
Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/004—Pressure suppression
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01D—SEPARATION
- B01D5/00—Condensation of vapours; Recovering volatile solvents by condensation
- B01D5/0057—Condensation of vapours; Recovering volatile solvents by condensation in combination with other processes
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01D—SEPARATION
- B01D50/00—Combinations of methods or devices for separating particles from gases or vapours
- B01D50/60—Combinations of devices covered by groups B01D46/00 and B01D47/00
-
- 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
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/16—Measuring radiation intensity
- G01T1/167—Measuring radioactive content of objects, e.g. contamination
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/16—Measuring radiation intensity
- G01T1/17—Circuit arrangements not adapted to a particular type of detector
- G01T1/178—Circuit arrangements not adapted to a particular type of detector for measuring specific activity in the presence of other radioactive substances, e.g. natural, in the air or in liquids such as rain water
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
-
- 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
- G21F9/008—Apparatus specially adapted for mixing or disposing radioactively contamined material
-
- 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
- B01D2257/202—Single element halogens
-
- 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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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- General Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- General Physics & Mathematics (AREA)
- Health & Medical Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Plasma & Fusion (AREA)
- Molecular Biology (AREA)
- Spectroscopy & Molecular Physics (AREA)
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- General Chemical & Material Sciences (AREA)
- Oil, Petroleum & Natural Gas (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention relates to the technical field of nuclear safety and radiation protection of ocean floating nuclear power platforms, and discloses a device for releasing pressure and discharging to ocean water under serious accidents of an ocean floating nuclear power device. The venturi water scrubber is used for removing most radioactive aerosol particles and radioactive iodine, condensing the discharged gas, and the metal fiber filter is used for removing radioactive aerosol particles with smaller particle size. The high-temperature and high-humidity mixed gas is discharged to sea water through the sea-going discharging device, so that the high-temperature steam in the mixed gas can be further condensed, and the mixed gas can be further used for absorbing radioactive aerosol and radioactive iodine in the mixed gas. The integrity of the containment of the reactor cabin is guaranteed, a large amount of radioactivity in the containment of the reactor cabin is released uncontrollably to the environment after serious accidents, and meanwhile, the radioactive influence of radioactive emission on the ocean floating nuclear power platform staff is reduced through seawater filtration.
Description
Technical Field
The invention relates to the technical field of nuclear safety and radiation protection of a marine floating nuclear power platform, in particular to a device for releasing pressure and discharging to seawater under severe accidents of a marine floating nuclear power device.
Background
The ocean floating nuclear power device is used as a nuclear facility for offshore movement, is a power source for ocean floating nuclear power propulsion and power supply, has frequent system operation working condition change, is limited by resource conditions such as space, weight and the like on a ship, and is simplified and optimized in the design of capacity and redundancy of a safety facility. Thus, the probability and risk of an accident for a marine floating nuclear power plant is relatively high, and the safety risk of a transition to a serious accident after a design basis accident is also relatively high, relative to a land-based nuclear facility. Once serious accidents happen to the ocean floating nuclear power plant, serious consequences such as fuel element damage, reactor core fusion, hydrogen explosion, stack cabin containment vessel overpressure and the like can be caused.
The containment vessel of the reactor is an important barrier for radioactive containment of the marine floating nuclear power plant after an accident, and corresponding measures must be taken to ensure the integrity thereof. The pressure bearing of the reactor containment is low and the internal free volume is small due to the limitation of the resource conditions such as space and weight on the ship, and in order to ensure the structural integrity of the reactor containment after serious accidents, an outward pressure relief and discharge system of the reactor containment is required to be arranged and is used for rapidly discharging radioactive steam in the reactor containment after serious accidents, so that the pressure of the reactor containment does not exceed a limit value; meanwhile, in the process of outwards releasing pressure and discharging, radioactive substances are removed in a filtering mode and the like, so that the influence of discharging on personnel and environment on a ship is reduced, and the radiation safety in the discharging process is ensured.
At present, the land nuclear power station comprehensively considers the relief measures of serious accidents, and a passive containment heat conduction system, a containment filtering and discharging system and the like are generally arranged to maintain the integrity of the containment. For the ocean floating nuclear power plant, the space and weight resources on the ship are limited, a high-power passive containment cooling system of a land-based nuclear power plant cannot be directly used, and large-scale filtering and discharging devices such as a sand bed filter and a metal fiber filter are difficult to remove radioactive substances. Therefore, the technical requirements on the integrity of the containment of the ship cabin after serious accidents of the ocean floating nuclear power plant are high, the difficulty is high, and reasonable outward pressure relief emission and radioactivity removal emission schemes are set by combining the environmental characteristics of the containment of the ship cabin, so that the integrity of the containment of the ship cabin is ensured, and the radiation safety of on-board workers and the environment is ensured.
Disclosure of Invention
Aiming at the defects in the prior art, the pressure relief and discharge device for the marine floating nuclear power plant to the seawater under serious accidents is provided, the structural integrity of the containment vessel of the reactor cabin is ensured, and in the serious accidents, radioactive steam in the containment vessel of the reactor cabin is rapidly discharged outwards, so that the pressure of the containment vessel of the reactor cabin does not exceed a limit value; in addition, in the process of outward pressure relief and emission, the influence of emission on personnel and environment on a ship is required to be reduced, and the radiation safety in the emission process is ensured.
The technical scheme adopted by the invention for solving the technical problems is as follows:
the utility model provides a marine floating nuclear power plant is to marine pressure release discharging equipment under serious accident which characterized in that: the device comprises a stacking cabin safety shell, an auxiliary cabin, a filtering and discharging device and a sea-going discharging device, wherein the stacking cabin safety shell is adjacent to the auxiliary cabin, and the auxiliary cabin is a sea-going cabin; a communication pipeline is arranged between the auxiliary cabin and the safety shell of the cabin, the outer wall of the communication pipeline is fixedly connected with the cabin wall in a sealing way, the inner side end of the communication pipeline is communicated with the inner space of the safety shell of the cabin, the outer side end of the communication pipeline is communicated with the inlet of the filter discharge device arranged in the auxiliary cabin, and electric safety isolation valves are arranged at both ends of the communication pipeline and both ends of the filter discharge device; the sea water through discharging device is arranged on the cabin wall of the auxiliary cabin adjacent to the sea water, one end of the sea water through discharging device is connected with the outlet of the filtering discharging device, and the other end of the sea water through the cabin wall of the auxiliary cabin adjacent to the sea water is communicated with the sea water; an electric stop valve and an electric stop check valve are sequentially arranged on a pipeline between the filtering and discharging device and the sea discharging device along the medium flowing direction.
According to the technical scheme, the filtering and discharging device adopts a mode of combining a Venturi water washer and metal fibers for filtering.
According to the technical scheme, the filtering and discharging device comprises a shell serving as a pressure container, and a mixed gas inlet pipeline, a Venturi water washing filter, a steam-water separator, a metal filter screen and a mixed gas outlet pipeline are sequentially arranged in the shell along the flowing direction of the mixed gas.
According to the technical scheme, the emergency discharging device also comprises an emergency discharging branch, the emergency discharging branch is connected with the filtering discharging device in parallel, and an electric safety isolating valve is arranged on the emergency discharging branch; the emergency discharge branch is connected between the communicating pipeline and the sea discharge device.
According to the technical scheme, the inlet end of the emergency discharge branch is connected between the electric safety isolation valve outside the communicating pipeline and the electric safety isolation valve at the inlet end of the filtering and discharging device, and the outlet end of the emergency discharge branch is connected between the electric safety isolation valve at the outlet end of the filtering and discharging device and the electric stop valve.
According to the technical scheme, the pipeline between the filtering and discharging device and the sea-going discharging device is provided with an out-of-pipe radioactivity on-line monitoring device.
According to the technical scheme, the on-line monitoring device for the radioactivity outside the pipe comprises a detection device, a local shielding shell and corresponding data processing equipment, wherein the detection device is attached to a pipeline between the filtering and discharging device and the sea-through discharging device, and the local shielding shell covers the detection device and the corresponding pipeline.
According to the technical scheme, the on-line monitoring device for radioactivity outside the pipe is positioned between the electric stop valve and the filtering and discharging device.
According to the technical scheme, in the pressure relief discharging device comprising the emergency discharging branch, the outside-pipe radioactivity on-line monitoring device is positioned between the outlet of the emergency discharging branch and the electric stop valve.
According to the technical scheme, the sea drainage device adopts a cylindrical barrel, and a plurality of through holes are formed in the cylindrical barrel at intervals; the diameter of the through hole is 5 mm-10 mm.
The invention has the following beneficial effects:
1. aiming at the risk of overpressure of the containment vessel of the reactor after a serious accident of the ocean floating nuclear power plant, combining the resource conditions on the ship and the environmental characteristics of the ship, a pressure relief emission scheme combining filtering and emission to seawater is provided, and the pressure relief emission is carried out on radioactive high-pressure steam in the containment vessel of the reactor; the integrity of the containment of the reactor cabin is guaranteed, a large amount of radioactivity in the containment of the reactor cabin is released uncontrollably to the environment after serious accidents, and meanwhile, the radioactive influence of radioactive emission on the ocean floating nuclear power platform staff is reduced through seawater filtration.
2. The filtering and discharging device adopts an integrated design idea, integrates a Venturi water-washing filter and a metal fiber filter in a shell serving as a pressure container, and simultaneously sets a steam-water separator to reduce the humidity of mixed gas entering the metal fiber filter, so that the filtering efficiency of radioactive aerosol and iodine is improved while the volume and the weight of the device are reduced.
The venturi water scrubber is used for removing most radioactive aerosol particles and radioactive iodine, condensing the discharged gas, and the metal fiber filter is used for removing radioactive aerosol particles with smaller particle size. The high-temperature and high-humidity mixed gas is discharged to sea water through the sea-going discharging device, so that the high-temperature steam in the mixed gas can be further condensed, and the mixed gas can be further used for absorbing radioactive aerosol and radioactive iodine in the mixed gas. In the process of outwards discharging the high-temperature and high-pressure mixed gas, according to the time of opening the discharge, a management and control measure is adopted for the periphery of the discharge pipeline, so that the radioactive influence on the staff of the ocean floating nuclear power platform in the discharge process is reduced.
3. The radioactivity of the outward discharged mixed gas is monitored on line in an on-line monitoring mode, and data support is provided for carrying out radioactive emission result evaluation, radiation protection measures and the like. The on-line monitoring device for the radioactivity outside the tube is arranged, the on-line monitoring device for the radioactivity outside the tube is partially shielded, the complexity of a monitoring system is reduced, the influence of the background on the monitoring result is reduced, and the reliability of the monitoring device is improved.
4. The sea discharging device can increase the contact area of the mixed gas discharged outwards and the seawater, increase the absorption efficiency of the seawater on radioactive aerosol and iodine, and reduce the influence of the radioactive discharge on the staff on the ocean floating platform.
Drawings
FIG. 1 is a schematic diagram of a relief to sea water discharge scheme in accordance with an embodiment of the present invention;
FIG. 2 is a schematic diagram of an embodiment of an on-line monitoring device for radioactivity outside a discharge conduit according to the present invention;
FIG. 3 is a schematic view of the structure of a filter drain device according to an embodiment of the present invention;
FIG. 4 is a schematic view of the structure of the sea displacement apparatus according to the present invention;
in the figure, 1, an auxiliary cabin; 2. a filter discharge device; 2-1, a shell; 2-2, a mixed gas inlet pipeline; 2-3, venturi water washing filter; 2-4, a steam-water separator; 2-5, a metal filter screen; 2-6, a mixed gas outlet pipeline; 3. sea-going discharge devices; 3-1, a cylinder; 3-2, through holes; 4. a stack safety housing; 5. sea; 6. a communication pipe; 7. an electric safety isolation valve; 8. an electric shut-off valve; 9. an electric shut-off check valve; 10. an emergency discharge branch; 11. an out-of-tube radioactivity on-line monitoring device; 11-1, a detection device; 11-2, a partial shielding shell; 12. a pipeline between the filter discharge device and the sea discharge device.
Detailed Description
The invention will now be described in detail with reference to the drawings and examples.
Referring to fig. 1 to 4, the ocean floating nuclear power plant provided by the invention is a device for releasing pressure and discharging to sea water in serious accidents.
Example 1
The marine filter comprises a pile cabin safety shell 4, an auxiliary cabin 1, a filter discharge device 2 and a marine discharge device 3, wherein the pile cabin safety shell is adjacent to the auxiliary cabin, and the auxiliary cabin is a sea 5 cabin; a communication pipeline 6 is arranged between the auxiliary cabin and the safety shell of the cabin, the outer wall of the communication pipeline is fixedly connected with the cabin wall in a sealing way, the inner side end of the communication pipeline is communicated with the inner space of the safety shell of the cabin, the outer side end of the communication pipeline is communicated with the inlet of the filter discharge device arranged in the auxiliary cabin, and electric safety isolation valves 7 are arranged at two ends of the communication pipeline and two ends of the filter discharge device; the sea water through discharging device is arranged on the cabin wall of the auxiliary cabin adjacent to the sea water, one end of the sea water through discharging device is connected with the outlet of the filtering discharging device, and the other end of the sea water through the cabin wall of the auxiliary cabin adjacent to the sea water is communicated with the sea water; an electric stop valve 8 and an electric stop check valve 9 are arranged in sequence along the medium flow direction on the pipeline between the filtering and discharging device and the sea discharging device.
In the embodiment, aiming at the risk of overpressure of the containment vessel of the reactor after a serious accident of the marine floating nuclear power plant, a decompression emission scheme combining filtration and emission to seawater is provided by combining the resource conditions on the ship and the environmental characteristics of the containment vessel, and the decompression emission is carried out on radioactive high-pressure steam in the containment vessel of the reactor; the integrity of the containment of the reactor cabin is guaranteed, a large amount of radioactivity in the containment of the reactor cabin is released uncontrollably to the environment after serious accidents, and meanwhile, the radioactive influence of radioactive emission on the ocean floating nuclear power platform staff is reduced through seawater filtration.
Example 2
Embodiment 2 differs from embodiment 1 in that, when the structure and principle are close to those of embodiment 1, it is: the filtering and discharging device adopts a mode of combining a Venturi water washer and metal fibers for filtering.
Specifically, the filtering and discharging device comprises a shell 2-1 serving as a pressure container, wherein a mixed gas inlet pipeline 2-2, a venturi water washing filter 2-3, a steam-water separator 2-4, a metal filter screen 2-5 and a mixed gas outlet pipeline 2-6 are sequentially arranged in the shell along the flowing direction of the mixed gas. The filtering and discharging device adopts an integrated design idea, integrates a Venturi water-washing filter and a metal fiber filter in a shell serving as a pressure container, and simultaneously sets a steam-water separator to reduce the humidity of mixed gas entering the metal fiber filter, so that the filtering efficiency of radioactive aerosol and iodine is improved while the volume and the weight of the device are reduced.
In this embodiment, a venturi scrubber is used to remove the vast majority of radioactive aerosol particles and radioactive iodine while condensing the exhaust gases, and a metal fiber filter is used to remove the smaller size radioactive aerosol particles. The high-temperature and high-humidity mixed gas is discharged to sea water through the sea-going discharging device, so that the high-temperature steam in the mixed gas can be further condensed, and the mixed gas can be further used for absorbing radioactive aerosol and radioactive iodine in the mixed gas. In the process of outwards discharging the high-temperature and high-pressure mixed gas, according to the time of opening the discharge, a management and control measure is adopted for the periphery of the discharge pipeline, so that the radioactive influence on the staff of the ocean floating nuclear power platform in the discharge process is reduced.
Example 3
Embodiment 3 differs from embodiment 1 in that when the structure and principle are close to those of embodiment 1, it is that: the emergency discharging branch circuit 10 is connected with the filtering discharging device in parallel, and an electric safety isolating valve is arranged on the emergency discharging branch circuit; the emergency discharge branch is connected between the communicating pipeline and the sea discharge device. When the filtering and discharging device can not timely discharge the radioactive high-pressure steam to the sea after being treated, the emergency discharging branch is opened.
In embodiment 3, preferably, the inlet end of the emergency discharge branch is connected between the electric safety isolation valve outside the communication pipe and the electric safety isolation valve at the inlet end of the filter discharge device, and the outlet end of the emergency discharge branch is connected between the electric safety isolation valve at the outlet end of the filter discharge device and the electric stop valve.
Example 4
Embodiment 4 differs from embodiments 1-3 in the structure and principle when it is close to those of embodiments in that: in order to acquire the outward emission radioactivity data, develop the result evaluation of the radioactivity emergency emission, provide important support for the staff on the floating nuclear power platform to carry out radiation protection measures and relevant emergency response, and be equipped with the outside-pipe radioactivity on-line monitoring device 11 on the pipeline 12 between the filtration emission device and the sea emission device.
The on-line monitoring device for radioactivity outside the pipe comprises a detection device 11-1, a local shielding shell 11-2 and corresponding data processing equipment, wherein the detection device is attached to a pipeline between the filtering and discharging device and the sea-going discharging device, and the local shielding shell covers the detection device and the corresponding pipeline. In this embodiment, the materials of the detection device, the partial shielding shell and the corresponding data processing equipment are all selected from the existing equipment or materials. The radioactivity of the outward discharged mixed gas is monitored on line in an on-line monitoring mode, and data support is provided for carrying out radioactive emission result evaluation, radiation protection measures and the like. The on-line monitoring device for the radioactivity outside the tube is arranged, the on-line monitoring device for the radioactivity outside the tube is partially shielded, the complexity of a monitoring system is reduced, the influence of the background on the monitoring result is reduced, and the reliability of the monitoring device is improved.
Specifically, the outside-tube radioactivity on-line monitoring device is positioned between the electric stop valve and the filtering and discharging device. In addition, in the pressure relief discharging device comprising the emergency discharging branch, the outside-pipe radioactivity on-line monitoring device is positioned between the outlet of the emergency discharging branch and the electric stop valve, so that the detection of the related data of the medium discharged into the sea water in the emergency condition is facilitated.
In the process of outwards discharging the high-temperature and high-pressure mixed gas, a management and control measure is adopted for the periphery of the discharge pipeline, so that the radioactive influence on the staff of the ocean floating nuclear power platform in the discharge process is reduced.
In the embodiment 1-4, the sea drainage device adopts a cylindrical barrel 3-1, and a plurality of through holes 3-2 are arranged on the cylindrical barrel at intervals; preferably, the diameter of the through hole is 5 mm-10 mm, and other diameter sizes of the through hole can be adopted.
In the embodiment, the sea-going discharging device can increase the contact area of the mixed gas discharged outwards and the sea water, increase the absorption efficiency of the sea water on radioactive aerosol and iodine, and reduce the influence of radioactive discharge on staff on the ocean floating platform.
The working principle of the invention is as follows:
through setting up small-size integrated filtration discharging equipment, carry out the decompression to the mixed steam of taking radioactivity, filter radioactive iodine and aerosol simultaneously, reduce the influence to floating nuclear power platform and environment, reduced the demand of system to total resource simultaneously. The seawater resource of the environment where the floating nuclear power platform is located is fully utilized, mixed steam with radioactivity is subjected to temperature reduction through the measure of discharging to seawater, meanwhile, radioactive iodine and aerosol are subjected to water washing and filtering, and the influence on workers of the floating nuclear power platform and the environment is reduced.
The foregoing is merely illustrative of the present invention and is not intended to limit the scope of the invention, which is defined by the claims and their equivalents.
Claims (10)
1. The utility model provides a marine floating nuclear power plant is to marine pressure release discharging equipment under serious accident which characterized in that: the device comprises a stacking cabin safety shell, an auxiliary cabin, a filtering and discharging device and a sea-going discharging device, wherein the stacking cabin safety shell is adjacent to the auxiliary cabin, and the auxiliary cabin is a sea-going cabin; a communication pipeline is arranged between the auxiliary cabin and the safety shell of the cabin, the outer wall of the communication pipeline is fixedly connected with the cabin wall in a sealing way, the inner side end of the communication pipeline is communicated with the inner space of the safety shell of the cabin, the outer side end of the communication pipeline is communicated with the inlet of the filter discharge device arranged in the auxiliary cabin, and electric safety isolation valves are arranged at both ends of the communication pipeline and both ends of the filter discharge device; the sea water through discharging device is arranged on the cabin wall of the auxiliary cabin adjacent to the sea water, one end of the sea water through discharging device is connected with the outlet of the filtering discharging device, and the other end of the sea water through the cabin wall of the auxiliary cabin adjacent to the sea water is communicated with the sea water; an electric stop valve and an electric stop check valve are sequentially arranged on a pipeline between the filtering and discharging device and the sea discharging device along the medium flowing direction.
2. The marine floating nuclear power plant severe accident pressure relief and discharge device according to claim 1, wherein: the filtering and discharging device adopts a mode of combining a Venturi water washer and metal fibers for filtering.
3. The marine floating nuclear power plant severe accident pressure relief and discharge device according to claim 2, wherein: the filtering and discharging device comprises a shell serving as a pressure container, and a mixed gas inlet pipeline, a Venturi water washing filter, a steam-water separator, a metal filter screen and a mixed gas outlet pipeline are sequentially arranged in the shell along the flowing direction of the mixed gas.
4. The marine floating nuclear power plant severe accident pressure relief and discharge device according to claim 1, wherein: the emergency discharging branch is connected with the filtering discharging device in parallel, and an electric safety isolating valve is arranged on the emergency discharging branch; the emergency discharge branch is connected between the communicating pipeline and the sea discharge device.
5. The marine floating nuclear power plant severe accident pressure relief and discharge device according to claim 4, wherein: the inlet end of the emergency discharge branch is connected between the electric safety isolation valve outside the communicating pipeline and the electric safety isolation valve at the inlet end of the filtering and discharging device, and the outlet end of the emergency discharge branch is connected between the electric safety isolation valve at the outlet end of the filtering and discharging device and the electric stop valve.
6. The marine floating nuclear power plant relief to sea water discharge apparatus according to any one of claims 1-5, wherein: an out-of-pipe radioactivity on-line monitoring device is arranged on the pipeline between the filtering and discharging device and the sea-going discharging device.
7. The marine floating nuclear power plant severe accident pressure relief and discharge device according to claim 6, wherein: the on-line monitoring device for radioactivity outside the pipe comprises a detection device, a local shielding shell and corresponding data processing equipment, wherein the detection device is attached to a pipeline between the filtering and discharging device and the sea-through discharging device, and the local shielding shell covers the detection device and the corresponding pipeline.
8. The marine floating nuclear power plant severe accident pressure relief and discharge device according to claim 6, wherein: the on-line monitoring device for radioactivity outside the tube is positioned between the electric stop valve and the filtering and discharging device.
9. The marine floating nuclear power plant severe accident pressure relief and discharge device according to claim 6, wherein: in the pressure relief discharge device comprising the emergency discharge branch, the out-of-pipe radioactivity on-line monitoring device is positioned between the outlet of the emergency discharge branch and the electric stop valve.
10. The marine floating nuclear power plant severe accident pressure relief and discharge device according to claim 5, wherein: the sea drainage device adopts a cylindrical barrel, and a plurality of through holes are formed in the cylindrical barrel at intervals; the diameter of the through hole is 5 mm-10 mm.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311546778.8A CN117594255A (en) | 2023-11-17 | 2023-11-17 | Device for releasing pressure to seawater under severe accident of ocean floating nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
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| CN202311546778.8A CN117594255A (en) | 2023-11-17 | 2023-11-17 | Device for releasing pressure to seawater under severe accident of ocean floating nuclear power plant |
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| CN202311546778.8A Pending CN117594255A (en) | 2023-11-17 | 2023-11-17 | Device for releasing pressure to seawater under severe accident of ocean floating nuclear power plant |
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