CN112509723A - Radioactive slurry treatment method and system - Google Patents
Radioactive slurry treatment method and system Download PDFInfo
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- CN112509723A CN112509723A CN202011260392.7A CN202011260392A CN112509723A CN 112509723 A CN112509723 A CN 112509723A CN 202011260392 A CN202011260392 A CN 202011260392A CN 112509723 A CN112509723 A CN 112509723A
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- 230000002285 radioactive effect Effects 0.000 title claims abstract description 116
- 239000002002 slurry Substances 0.000 title claims abstract description 88
- 238000000034 method Methods 0.000 title claims abstract description 37
- 238000001035 drying Methods 0.000 claims abstract description 66
- 239000000706 filtrate Substances 0.000 claims abstract description 44
- 239000004568 cement Substances 0.000 claims abstract description 42
- 239000007788 liquid Substances 0.000 claims abstract description 32
- 238000007711 solidification Methods 0.000 claims abstract description 31
- 230000008023 solidification Effects 0.000 claims abstract description 31
- 238000007789 sealing Methods 0.000 claims abstract description 27
- 238000000926 separation method Methods 0.000 claims abstract description 14
- 238000001914 filtration Methods 0.000 claims description 121
- 238000003860 storage Methods 0.000 claims description 34
- 239000000203 mixture Substances 0.000 claims description 25
- 238000010438 heat treatment Methods 0.000 claims description 15
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 15
- 238000001816 cooling Methods 0.000 claims description 9
- 238000003828 vacuum filtration Methods 0.000 claims description 7
- 239000011148 porous material Substances 0.000 claims description 3
- 230000000694 effects Effects 0.000 abstract description 9
- 239000007789 gas Substances 0.000 description 84
- 239000000126 substance Substances 0.000 description 16
- 239000007787 solid Substances 0.000 description 12
- 239000002699 waste material Substances 0.000 description 11
- 230000005855 radiation Effects 0.000 description 10
- 239000000941 radioactive substance Substances 0.000 description 8
- 239000002901 radioactive waste Substances 0.000 description 6
- 238000005406 washing Methods 0.000 description 6
- 238000009835 boiling Methods 0.000 description 5
- 239000002245 particle Substances 0.000 description 5
- 238000003915 air pollution Methods 0.000 description 4
- 238000009833 condensation Methods 0.000 description 4
- 230000005494 condensation Effects 0.000 description 4
- 239000007790 solid phase Substances 0.000 description 4
- 229910000831 Steel Inorganic materials 0.000 description 3
- 238000011010 flushing procedure Methods 0.000 description 3
- 239000010959 steel Substances 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 2
- 239000002826 coolant Substances 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 238000002955 isolation Methods 0.000 description 2
- 238000005259 measurement Methods 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 239000008399 tap water Substances 0.000 description 2
- 235000020679 tap water Nutrition 0.000 description 2
- 238000012546 transfer Methods 0.000 description 2
- 238000011144 upstream manufacturing Methods 0.000 description 2
- 238000003466 welding Methods 0.000 description 2
- 238000004140 cleaning Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 239000002927 high level radioactive waste Substances 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000002156 mixing Methods 0.000 description 1
- 238000003672 processing method Methods 0.000 description 1
- 238000005086 pumping Methods 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
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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
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/16—Processing by fixation in stable solid media
- G21F9/162—Processing by fixation in stable solid media in an inorganic matrix, e.g. clays, zeolites
- G21F9/165—Cement or cement-like matrix
-
- 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
- G21F9/04—Treating liquids
- G21F9/06—Processing
-
- 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
- G21F9/28—Treating solids
- G21F9/30—Processing
-
- 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
- G21F9/28—Treating solids
- G21F9/34—Disposal of solid waste
- G21F9/36—Disposal of solid waste by packaging; by baling
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- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Inorganic Chemistry (AREA)
- Environmental & Geological Engineering (AREA)
- Treatment Of Sludge (AREA)
- Drying Of Solid Materials (AREA)
Abstract
The invention discloses a radioactive slurry treatment method, which comprises the following steps: s1, performing solid-liquid separation on the radioactive slurry to obtain filtrate and filter residue; s2, drying the filter residue to obtain dry filter residue; s3, sealing the dry filter residue; and S4, carrying out cement solidification treatment on the filtrate. The invention also discloses a radioactive slurry treatment system. The method can solve the problem of treatment of radioactive slurry with high alpha nuclide content, and has convenient operation and good treatment effect.
Description
Technical Field
The invention belongs to the technical field of nuclear industry, and particularly relates to a radioactive slurry treatment method and system.
Background
When nuclear facilities are retired, radioactive slurry often appears in a large radioactive waste liquid storage tank, and the radioactive slurry is characterized by containing a large amount of alpha nuclide, the alpha nuclide is mainly distributed in solid-phase slurry, the existing radioactive slurry treatment modes such as cement solidification and the like are mainly used for treating low-level radioactive slurry, the radioactivity level of the alpha nuclide is high, the treatment modes such as cement solidification and the like cannot be directly adopted for treatment, and at present, the treatment of the slurry with high content of the alpha nuclide and the like in China has no mature engineering experience for reference.
Disclosure of Invention
Aiming at the defects in the prior art, the invention provides a radioactive slurry treatment method and a radioactive slurry treatment system, which can solve the problem of treatment of radioactive slurry with high alpha nuclide content.
According to one aspect of the invention, a radioactive slurry treatment method is provided, which has the technical scheme as follows:
a radioactive mud treatment method, comprising:
s1, performing solid-liquid separation on the radioactive slurry to obtain separated filtrate and filter residue;
s2, drying the filter residue to obtain dry filter residue;
s3, sealing the dry filter residue;
and S4, carrying out cement solidification treatment on the filtrate.
Preferably, the method further comprises the following steps:
and S5, condensing the gas mixture generated when the filter residue is dried in the step S2, and carrying out cement solidification treatment on the generated condensate.
Preferably, in step S1, the radioactive slurry is subjected to solid-liquid separation, specifically vacuum filtration using a filter bag,
the relative vacuum degree of vacuum filtration is 10-93 KPa, and the filtration pore diameter of the filter bag is 10-500 μm.
Preferably, the drying treatment is to heat the filter residue by adopting hot gas, and the temperature of the hot gas is 90-110 ℃; and/or the presence of a gas in the gas,
and the drying treatment is to heat the filter residue by adopting a heater, wherein the heating temperature of the heater is 90-110 ℃.
Preferably, the water content of the dry filter residue is less than or equal to 1 percent.
According to another aspect of the invention, a radioactive mud treatment system is provided, which comprises the following technical scheme:
a radioactive mud treatment system, comprising: a filtering device, a drying device, a cement solidifying device and a sealing device,
the filtering device is used for introducing radioactive slurry and filtering and separating the radioactive slurry to obtain filter residue and filtrate;
the drying device is used for drying the filter residue in the filtering device to obtain dry filter residue;
the cement solidification device is used for carrying out cement solidification treatment on filtrate obtained by filtering in the filtering device;
and the sealing device is used for sealing the dry filter residue obtained after drying by the drying device.
Preferably, the filtering apparatus includes a filtering container, a vacuum device and a first storage tank,
a feeding pipeline is arranged on the filtering container;
the vacuum equipment is communicated with the filtering container and is used for vacuumizing the interior of the filtering container;
the first storage tank is communicated with the filtering container and is used for receiving filtrate generated after filtering in the filtering container.
Preferably, a level meter is arranged in the filtering container and used for measuring the height of the radioactive slurry in the filtering container and sending an electric signal when the measured height value reaches a preset height threshold value;
and a feeding valve is arranged on the feeding pipeline, is electrically connected with the level meter and is used for controlling the feeding valve to be closed according to an electric signal sent by the level meter.
Preferably, the drying device comprises an air inlet line communicating with the filter container and a first heater for heating the gas in the air inlet line to form a hot gas;
and/or the drying device comprises a second heater which is arranged outside the filtering container and used for heating the filtering container.
Preferably, the system further comprises a condensing means,
the condensing device comprises a condenser and a second storage tank,
an inlet of the condenser is communicated with the filtering container and is used for cooling a gas mixture generated when the drying device dries the filter residue;
and the second storage tank is communicated with an outlet of the condenser and is used for receiving condensate obtained by cooling in the condenser.
The radioactive slurry treatment method and the radioactive slurry treatment system have the following beneficial effects:
(1) the solid-liquid separation can be carried out on the radioactive slurry, so that the solid content in the radioactive slurry (filtrate) is reduced, filter residue with high radioactivity level (the activity concentration of the alpha nuclide is about E +7Bq/Kg) and filtrate with low radioactivity level (the activity concentration of the alpha nuclide is less than or equal to E +5Bq/Kg) are obtained, the filtrate can be directly treated by cement solidification and other modes, the filter residue is sealed and stored by a special disposal barrel for radioactive waste, the treatment effect is good, the problem that the high-level radioactive slurry cannot be treated by the traditional technology can be solved, and the method can be suitable for the export engineering of the radioactive slurry with high alpha nuclide content.
(2) By arranging the condensing device, steam and low-boiling-point substances generated by drying can be recovered, the content of harmful substances such as radioactive substances in tail gas is reduced, and the air pollution is reduced.
(3) The method is not limited by the radiation level of the radioactive slurry, is suitable for all types of radioactive slurries, can be conveniently controlled by remote control in the treatment process, and can avoid the high radioactive irradiation risk caused by manual close-range operation.
Drawings
FIG. 1 is a schematic flow diagram of a radioactive mud treatment method according to an embodiment of the present invention;
fig. 2 is a schematic structural diagram of a radioactive mud treatment system according to an embodiment of the present invention.
Wherein, 1-a filtration vessel; 2-vacuum equipment; 3-a first storage tank; 4-a feed line; 5-a third storage tank; 6-a feed valve; 7-a bypass line; 8-a discharge line; 9-a discharge valve; 10-a cement curing device; 11-a buffer tank; 12-an isolation valve; 13-tail gas treatment process; 14-an air intake line; 15-an air inlet valve; 16-a gas supply device; 17-air outlet pipeline; 18-a fan; 19-a second heater; 20-a condenser; 21-a second storage tank; 22-a delivery pump; 23-a waste bin; 24-waste disposal reservoir.
Detailed Description
The technical solution of the present invention will be described clearly and completely with reference to the accompanying drawings, and it should be understood that the described embodiments are a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be obtained by a person skilled in the art without any inventive step based on the embodiments of the present invention, are within the scope of the present invention.
Aiming at the problems that the prior art is difficult to treat high-level radioactive slurry and the like, the invention provides a radioactive slurry treatment method, which comprises the following steps:
s1, performing solid-liquid separation on the radioactive slurry to obtain filtrate and filter residue;
s2, drying the filter residue to obtain dry filter residue;
s3, sealing the dry filter residue;
and S4, carrying out cement solidification treatment on the filtrate.
Correspondingly, the invention also provides a radioactive slurry treatment system, which comprises a filtering device, a drying device, a cement curing device and a sealing device,
the filtering device is used for filtering the radioactive slurry to obtain filter residue and filtrate;
the drying device is used for drying the filter residue in the filtering device;
the cement solidification device is used for carrying out cement solidification treatment on filtrate obtained by filtering the filtering device;
and the sealing device is used for sealing the dry filter residue obtained after drying by the drying device.
Example 1
As shown in fig. 1, the present embodiment discloses a radioactive slurry treatment method, including:
s1, performing solid-liquid separation on the radioactive slurry to obtain filtrate and filter residue.
Wherein alpha nuclide with high radioactivity level (the radioactivity concentration of the alpha nuclide is more than or equal to E +5Bq/Kg) in the radioactive slurry is mainly distributed in the solid-phase slurry, and the solid content of the radioactive slurry (filtrate) can be reduced through solid-liquid separation, so that the radioactive slurry (filtrate) can be treated by adopting cement solidification and other modes.
Specifically, the radioactive slurry is introduced into a filter bag (or a filter screen) in a filter container through a feeding pipeline, vacuum filtration is carried out under the pushing of a relative vacuum degree or pressure difference generated by vacuumizing the filter container, so that liquid in the radioactive slurry and part of solid particles with small particles are filtered from holes of the filter bag to obtain filtrate, the filtrate flows into a filtrate receiving tank for temporary storage, and the solid particles with larger particle sizes in the radioactive slurry are trapped in the filter bag to form filter residue. The radioactivity of the alpha nuclide in the filtrate in the embodiment is less than or equal to E +5 Bq/Kg.
In the embodiment, the relative vacuum degree generated by vacuumizing the filtering container in the vacuum filtering process is preferably 10-93 KPa, so that a better filtering effect is achieved. In this embodiment, the vacuum pump is used to evacuate the filtering container, so that the maximum relative vacuum degree can be provided by not less than 80KPa, and the relative vacuum degree required by the vacuum filtering requirement can be completely provided.
In the embodiment, the aperture of the filter bag or the filter screen in the vacuum filtration process is 10-500 μm. More preferably, the aperture of the filter bag or the filter screen can be 10-100 μm, and the filter bag or the filter screen can be used for filtering mud with low solid content (the volume percentage content of the solid phase does not exceed 20% of the volume of the mud); or the aperture of the filter bag or the filter screen can be 100-500 mu m, and the filter bag or the filter screen can be used for filtering slurry with high solid content (the volume percentage content of the solid phase exceeds 20% of the volume of the slurry).
Considering that the radioactive slurry in the embodiment contains a large amount of high-level radioactive alpha nuclide, in the embodiment, a level meter is arranged in the filtering container to perform limit measurement on the height of the introduced radioactive slurry, a feed valve interlocked with the level meter is arranged on the feed pipe line, automatic interlocking control is performed when the radioactive slurry is introduced, and when the level meter detects that the height of the radioactive slurry in the filtering container reaches the limit height of the filtering container, the feed valve on the radioactive slurry pipe line is closed through automatic interlocking to complete feeding, so that the radioactive radiation risk existing in manual operation can be avoided.
In this embodiment, after the radioactive slurry is fed into the filtering container, the method further includes: and (3) washing the radioactive slurry pipeline, for example, washing the pipeline by using tap water or other low-level radioactive clear liquid, and introducing the washed water into a filtering container to be filtered together with radioactive silt.
And S2, drying the filter residue to obtain dry filter residue.
In an optional embodiment, hot gas is introduced into the filtering container, and the filter residue is heated and dried through heat exchange between the hot gas and the filter residue obtained by filtering, so that moisture in the filter residue is evaporated into steam, and the dry filter residue is obtained. And the steam, the hot gas and other gas mixtures are discharged through an air outlet pipeline arranged on the filtering container, and negative pressure is pumped at the air outlet pipeline side of the filtering container, so that the steam generated by drying is quickly discharged from the filtering container through the air outlet pipeline under the pushing of the negative pressure. In the embodiment, the hot gas is preferably compressed air, and the flow rate of the compressed air is preferably 5-500L/min; the temperature of the hot gas is preferably 90-110 ℃.
In another alternative embodiment, the filter residue in the filter container may be directly heated by a heater to evaporate water from the filter residue into steam, resulting in a dry filter residue. The gas mixture such as steam is discharged through an air outlet pipeline arranged on the filtering container, and negative pressure is pumped at the air outlet pipeline side of the filtering container, so that the steam generated by drying is rapidly discharged from the filtering container through the air outlet pipeline under the pushing of the negative pressure. In this embodiment, the heating temperature of the heater is preferably 90 to 110 ℃.
Of course, the filter residue can also be dried simultaneously by adopting two modes of introducing hot gas and directly heating.
In this embodiment, the drying process of the filter residue obtained by filtering further includes: and detecting the humidity of the gas discharged from the gas outlet of the filter container, and judging whether the filter residue is dried or not by detecting the humidity so as to determine the drying end point of the filter residue. In order to ensure that the filter residue is fully dried, the water content of the dry filter residue in the embodiment is less than 1%, the humidity of the gas discharged from the gas outlet of the filter container is 1-10%, and the filter residue can be specifically selected according to different material compositions.
And S3, sealing the dry filter residue.
And S4, carrying out cement solidification treatment on the filtrate.
Specifically, in step S3, the dry residue is transferred to a storage container capable of containing high-level radioactive waste, for example, the dry residue together with the filter bag can be taken out of the filter container by using a tool such as a manipulator or a crane, and then put into a steel waste barrel capable of resisting radioactive radiation, and sealed by welding, and then transferred to a radioactive waste disposal warehouse for storage after being loaded into the barrel, thereby completing the residue treatment. And step S4, introducing the filtrate obtained by solid-liquid separation into a cement solidification device, mixing the filtrate with cement to form a mixture, solidifying the mixture to form a cement solidified body, and finishing the treatment of the filtrate.
Considering that, in the drying process of the filter residue, besides the water is evaporated, some low-boiling-point substances with boiling points close to or lower than that of water may exist in the filter residue and may be volatilized into gas by heating, that is, the gas generated in the drying process of the filter container includes steam, gaseous low-boiling-point substances, and gas introduced in the drying process, which are collectively referred to as a gas mixture, and the gas mixture may contain some radioactive substances with low boiling points and may be directly discharged to cause air pollution. Therefore, the processing method in this embodiment further includes:
and S5, condensing the gas mixture generated by the drying treatment, and carrying out cement solidification treatment on the condensate.
Specifically, a gas mixture containing steam generated in the drying process is introduced into a condenser for cooling and condensation, the cooling temperature of the condenser is preferably 20-25 ℃, the steam and other low-boiling-point substances with the same or similar boiling points as water in the gas mixture are condensed into liquid, the condensed liquid obtained by condensation is introduced into a cement solidification device and is mixed with cement to form a mixture, the mixture is solidified to form a cement solidified body, and the filtrate treatment is completed. The uncondensed gas discharged from the condenser is introduced into a tail gas treatment process, for example, the uncondensed gas is introduced into a washing tower for washing, then is preheated, and then is introduced into a tail gas filtering unit for filtering treatment, so that harmful substances such as radioactive substances in the tail gas are further removed, and the treated tail gas is sent to a nuclear power plant exhaust center to complete treatment and discharge.
The radioactive slurry treatment method in the embodiment obtains high-level radioactive solid radiation and low-level radioactive liquid radiation by performing solid-liquid separation treatment on radioactive slurry, drying the separated solid radiation, condensing a gas mixture generated by drying, hermetically storing the dried high-level radioactive solid radiation in a waste barrel specially used for accommodating radioactive waste, and directly treating the low-level radioactive liquid radiation and a condensate generated by condensation in a cement solidification mode and the like, thereby solving the problem that the prior art cannot treat the high-level radioactive slurry with high content of alpha nuclide, meanwhile, the method is also suitable for treating the low-level radioactive slurry, the treatment effect of the low-level radioactive slurry can be further improved, namely the method is not limited by the radioactive level of the slurry, the device is suitable for all types of radioactive mud, and the treatment process can be conveniently controlled by remote control, so that the high radioactive irradiation risk caused by manual close-range operation can be avoided.
Example 2
As shown in fig. 2, the present embodiment discloses a radioactive mud treatment system, which includes a filtering device, a drying device, a cement solidifying device, and a sealing device, wherein: the filtering device is used for introducing radioactive slurry and filtering the radioactive slurry to obtain filter residue and filtrate; the drying device is used for drying the filter residue in the filtering device to obtain dry filter residue; the cement solidification device is used for carrying out cement solidification treatment on the filtrate obtained in the filtering device; and the sealing device is used for sealing the dry filter residue obtained in the drying device.
In particular, the filtration apparatus comprises a filtration vessel 1, a vacuum device 2 and a first reservoir 3. A feed line 4 is provided on the filter vessel 1, preferably at the top of the filter vessel 1, for feeding radioactive slurry into the filter vessel 1. Upstream of the feed line 4, a third storage tank 5 may be provided for temporary storage of radioactive mud. Downstream of the feed line 4, a feed valve 6 is provided to control the feeding of the radioactive slurry into the filtering container 1. A feed pump may also be provided on the feed line 4 to deliver the radioactive slurry. In this embodiment, the feed line 4 may further include a bypass line 7 connected thereto, and the bypass line 7 is internally filled with production water, such as tap water, for flushing the feed line 4 and the feed valve 6 after the feed line 4 completes the feed, the flushing water enters the filter container 1 and is filtered together with the introduced radioactive slurry, and after the flushing is completed, the bypass line 7 is closed. The filtering container 1 is internally provided with a filtering bag (or a filtering net), the introduced radioactive slurry enters the filtering bag, the filtrate is filtered out from the filtering bag, and most of solid particles containing alpha nuclide are intercepted in the filtering bag, namely filter residue, so that the radiation level of the radioactive slurry in the filtrate is reduced, and the subsequent cement solidification treatment is convenient. In the embodiment, the aperture of the filter bag is preferably 10-500 μm, and the filter efficiency can be properly improved by selecting a proper aperture of the filter bag on the basis of meeting the filter requirement. The top of the filtering container is provided with a sealing cover which is movably connected so as to install the filtering bag and take out filter residues generated by filtering after the filtering is finished.
In this embodiment, a level meter is further disposed in the filtering container 1, the level meter and the feed valve 6 are under interlocking control, that is, the level meter is electrically connected to the feed valve and is used for performing limit measurement on the height of radioactive slurry introduced into the filtering container, a limit height threshold value for the introduced radioactive slurry is set on the level meter, an electrical signal is sent when the height value measured by the level meter reaches the preset height threshold value, the feed valve 6 controls the feed valve to be automatically closed when receiving the electrical signal sent by the level meter, automatic radioactive slurry feeding is completed, and radioactive irradiation risk caused by close-range operation of a worker can be avoided.
The bottom or the lower part of filtering container 1 are equipped with the liquid outlet, and first storage tank 3 passes through ejection of compact pipeline 8 intercommunication with the liquid outlet of filtering container 1, is equipped with bleeder valve 9 on the ejection of compact pipeline 8 to the switching of control ejection of compact pipeline 8, the filtrating produced filtrating of discharge, first storage tank 3 is used for receiving and the above-mentioned filtrating of keeping in. The vacuum equipment is communicated with the filtering container 1 and is used for vacuumizing the interior of the filtering container 1 so as to provide the relative vacuum degree required by filtering the radioactive slurry and promote the filtering effect of the filtering net, namely vacuum filtering. The relative vacuum degree generated by vacuumizing the filtering container 1 by the vacuum equipment is preferably 10-93 KPa, so that a good filtering effect is ensured.
In this embodiment, the vacuum apparatus 2 may adopt a vacuum pump, the maximum relative vacuum degree that the vacuum pump can provide is not less than 80KPa, the vacuum pump is communicated with the liquid outlet of the filter container 1 through the first storage tank 3, the radioactive slurry in the filter container 1 is subjected to vacuum filtration by vacuumizing through the vacuum pump, so as to realize rapid filtration, and the filtered filtrate flows into the first storage tank 3 for temporary storage. And a liquid outlet of the first storage tank 3 is connected to a cement solidification device 10 for carrying out cement solidification treatment on the filtrate generated by filtration. A buffer tank 11 and an isolation valve 12 are also arranged between the vacuum pump and the first storage tank 3 to prevent filtrate from being sucked back to the vacuum pump. The gas outlet of the vacuum pump is connected to the tail gas treatment process 13, so as to prevent harmful gases such as radioactive substances from directly entering the atmospheric environment to cause pollution.
In some alternative embodiments, the drying device in this embodiment comprises an air inlet line 14, the outlet of which air inlet line 14 communicates with the filter container 1, and a first heater for heating the gas in the air inlet line 14 to form hot gas. Specifically, the outlet of the air inlet line 14 can be set to communicate with the liquid outlet of the filtering container 1, or with the outlet line 8 communicating with the liquid outlet, as shown in fig. 2, the air inlet line 14 is provided with an air inlet valve 15, and during filtering, the air inlet valve 15 is closed and the outlet valve 9 is opened; at drying, the inlet valve 9 is closed and the inlet valve 15 is opened. The inlet of the air inlet pipeline 14 is used for communicating with the gas supply device 16, a first heater (not shown in the figure) is arranged at the upstream of the air inlet pipeline, for example, the first heater can be arranged between the gas supply device 16 and the air inlet valve, or an electric tracing is arranged on the air inlet pipeline as the first heater and used for heating the gas supplied by the gas supply device 16, the heated gas is introduced into the filter container 1 and exchanges heat with the filter residue in the filter container 1, so that the moisture in the filter residue is evaporated into steam, and the dry filter residue is obtained. An air outlet pipeline 17 is arranged on the filtering container 1, the air outlet pipeline 17 is communicated with a condensing device to discharge steam generated by drying, and a fan 18 and other similar devices are arranged on the air outlet pipeline side of the filtering container 1 to pump negative pressure, so that the steam is quickly discharged from the filtering container 1 through the air outlet pipeline 17 under the pushing of the negative pressure. In this embodiment, the gas supply device 16 may be a compressor, the gas is compressed air, and the flow rate of the compressed air is preferably 5 to 500L/min; the first heater may be a commercially available electric heater or electromagnetic heater, and the temperature of the heated gas (compressed air) is preferably 90 to 110 ℃. After the drying is completed, the system treatment efficiency can also be improved by only turning on the gas supply device 16 (air compressor) and introducing cold or normal temperature gas (compressed air) into the filter container 1 to rapidly cool the dry filter residue, for example, to room temperature.
In another alternative embodiment, the drying device in this embodiment includes a second heater 19. The second heater 19 is sleeved outside the filtering container 1 and used for heating the filtering container 1 to evaporate water in the filter residue into steam, so as to obtain dry filter residue. At this time, the filtering container 1 is also provided with an air outlet pipeline 17, the air outlet pipeline 17 is communicated with a condensing device to discharge steam generated by drying, and a fan 18 and the like are arranged on the air outlet pipeline side of the filtering container 1 to draw negative pressure, so that the steam is quickly discharged from the filtering container 1 through the air outlet pipeline 17 under the pushing of the negative pressure. In this embodiment, the second heater 19 may be an electric heater or an electromagnetic heater, and the heating temperature is preferably 90-110 deg.C
Of course, the drying device of this embodiment may also adopt the above two drying devices to dry at the same time, and simultaneously adopt the mode of introducing hot gas and directly heating to dry the filter residue at the same time, that is, the drying device simultaneously includes the air inlet pipeline 14, the first heater, the second heater 19 and other equipment, and its specific connection mode is as described above, and will not be described herein again.
In this embodiment, the air outlet pipeline 17 may be provided with a humidity detector for determining the drying end point by determining the drying degree of the filter residue according to the humidity of the air discharged from the filter container 1 in the drying process.
Specifically, the sealing device of the present embodiment includes a waste bin 23 and a transfer device. The waste barrel can adopt a waste barrel special for radioactive waste, for example, a steel barrel resistant to high-level radioactive radiation is adopted for sealing and storing dry filter residues, and the sealing mode can adopt welding and other modes. The transfer equipment can adopt a mechanical arm, a crane and the like and is used for taking out dry filter residues in the filter container 1, sealing and storing the dry filter residues in the waste barrel 23, transferring the filter residues to the waste disposal warehouse 24 for storage after the filter residues are placed in the barrel, and finishing filter residue treatment.
In the drying process of the filter residue, besides the moisture is evaporated, low-boiling-point substances which may have some boiling points close to or lower than that of water in the filter residue can be heated and volatilized into gas, that is, the gas discharged from the gas outlet line 17 in the filter container 1 comprises steam, gaseous low-boiling-point substances and gas introduced in the drying process, the gas in the gas outlet line 17 is generally called gas mixture, and the gas mixture is directly discharged to possibly cause atmospheric pollution. Therefore, the radioactive slurry treatment system in this embodiment may further include a condensing device for condensing the gas mixture discharged from the filtering container 1 to condense the steam and low boiling point substances therein into liquid, so as to reduce the content of harmful substances such as radioactive substances contained in the uncondensed gas and reduce air pollution.
Specifically, the condensing means includes a condenser 20 and a second storage tank 21. The inlet of the condenser 20 communicates with the filter vessel 1 via the gas outlet line 17 for the passage of the gas mixture produced during the drying process in the filter vessel 1 and for cooling the gas mixture. The temperature of the cooling medium in the condenser 20 is preferably 20-25 ℃, so that steam and low-boiling-point substances in the gas mixture are quickly condensed into liquid to obtain condensate, and the condensate is discharged through a liquid outlet on the condenser 20. The cooling medium in the condenser 20 of this embodiment can be circulating water at normal temperature. The second storage tank 21 is communicated with a liquid outlet of the condenser 20, and is used for receiving and temporarily storing condensate obtained by cooling in the condenser 20. The second storage tank 21 is also communicated with the cement solidification device 10, and the condensate in the second storage tank 21 can be conveyed to the cement solidification device 10 through the conveying pump 22 for cement solidification treatment. The gas outlet of the condenser is communicated with the tail gas treatment process 13, for example, the condenser can be communicated with a washing tower and then communicated with a preheater, etc., the uncondensed gas in the condenser 20 is discharged through the gas outlet of the condenser 20, and then enters the washing tower to be washed, then enters the preheater to be preheated, etc., and then is introduced into a tail gas filtering unit to be filtered, so that harmful substances such as radioactive substances in the tail gas are further removed, and the treated tail gas is sent to the exhaust center of the nuclear power plant to finish treatment and discharge.
The radioactive mud treatment system of the embodiment has the following beneficial effects:
(1) the solid-liquid separation can be carried out on the radioactive slurry, so that the solid content in the radioactive slurry (filtrate) is reduced, high-level radioactive filter residues and low-level radioactive filtrate are obtained, the filtrate can be directly treated in modes of cement solidification and the like, the filter residues are stored in a special radioactive waste disposal barrel in a sealing mode, the treatment effect is good, the problem that the high-level radioactive slurry cannot be treated in the traditional technology can be solved, and the method is suitable for the export engineering of the radioactive slurry with high alpha nuclide content.
(2) By arranging the condensing device, steam and low-boiling-point substances generated by drying can be recovered, the content of harmful substances such as radioactive substances in tail gas is reduced, and the air pollution is reduced.
Example 3
The embodiment discloses a radioactive slurry treatment method, which adopts the treatment system in the embodiment 2 to treat radioactive slurry with high alpha nuclide content, and comprises the following specific steps:
(1) the sealing lid of the filtration vessel 1 is opened, and a filtration bag having a pore size of 500 μm is installed in the filtration vessel 1 by a robot or a crane, and the sealing lid is restored and sealed.
(2) And opening the feed valve 6, introducing the radioactive slurry in the third storage tank 5 into a filter bag in the filter container 1 at a flow rate of 20-50L/min, and closing the feed valve 6 in a linkage manner when the level meter detects that the introduced radioactive slurry reaches a set limit height.
(3) The bypass line 7 is opened and the feed line 4 is flushed with cleaning water.
(4) And starting the vacuum pump 2, pumping negative pressure to the filtering container 1, filtering the radioactive slurry in the filtering bag under the action of the negative pressure, allowing the filtrate to flow into the first storage tank 3, and leaving filter residues in the filtering bag, namely, the solid-liquid separation process.
(5) And after the solid-liquid separation is finished, closing the vacuum pump, opening the drying device, and introducing 90-110 ℃ compressed air at a flow rate of 100-200L/min if an air inlet pipeline and the first heater are opened, and/or opening the second heater to heat the filtering container to 90-110 ℃ so that the water in the filter residue is evaporated into steam, namely the drying process.
(6) Meanwhile, the fan 18 is turned on, and the mixture of the vapor and the introduced compressed air is discharged into the condenser 20 through the gas outlet pipeline 17 for cooling, so that the vapor and the low-boiling-point substances in the gas are condensed into liquid, and a condensate is obtained, namely the condensation process. The condensate is discharged into a second storage tank 21 for temporary storage, and the uncondensed gas is conveyed to the tail gas treatment process 13 through a fan 18 for tail gas treatment. When it is detected that the humidity of the gas in the gas outlet line 17 is less than a certain value (for example, the humidity is 5%, which can be obtained by performing tests according to the composition of the gas), the drying device is turned off.
(7) After the drying and condensing process is completed, the sealing cover of the filtering container 1 is opened, the filter residue and the filter bag are transferred to a waste barrel 23 (e.g. a 200L steel barrel) for sealing by means of a mechanical arm or a crane, and then transferred to a waste disposal warehouse 24 for storage, i.e. the treatment of the high-level solid radioactive substance is completed.
(8) The filtrate in the first reservoir 3 and the condensate in the second reservoir 21 are sent to the cement solidification apparatus 10, and mixed with cement or the like to form a cement solidified body, thereby completing the treatment of the filtrate and the condensate with a low radioactivity level.
It will be understood that the above embodiments are merely exemplary embodiments taken to illustrate the principles of the present invention, which is not limited thereto. It will be apparent to those skilled in the art that various modifications and improvements can be made without departing from the spirit and substance of the invention, and these modifications and improvements are also considered to be within the scope of the invention.
Claims (10)
1. A radioactive mud treatment method, comprising:
s1, performing solid-liquid separation on the radioactive slurry to obtain separated filtrate and filter residue;
s2, drying the filter residue to obtain dry filter residue;
s3, sealing the dry filter residue;
and S4, carrying out cement solidification treatment on the filtrate.
2. The radioactive mud treatment method of claim 1, further comprising:
and S5, condensing the gas mixture generated when the filter residue is dried in the step S2, and carrying out cement solidification treatment on the generated condensate.
3. The radioactive slurry treatment method according to any one of claims 1 to 2, wherein in step S1, the radioactive slurry is subjected to solid-liquid separation, specifically, vacuum filtration using a filter bag,
the relative vacuum degree of vacuum filtration is 10-93 KPa, and the filtration pore diameter of the filter bag is 10-500 μm.
4. The radioactive mud treatment method according to any one of claims 1 to 2, wherein the drying treatment is heating the filter residue by using hot gas, and the temperature of the hot gas is 90 to 110 ℃; and/or the presence of a gas in the gas,
and the drying treatment is to heat the filter residue by adopting a heater, wherein the heating temperature of the heater is 90-110 ℃.
5. The method for treating radioactive mud according to any one of claims 1 to 2, wherein the water content of the dry filter residue is less than or equal to 1%.
6. A radioactive mud treatment system, comprising: a filtering device, a drying device, a cement solidifying device and a sealing device,
the filtering device is used for introducing radioactive slurry and filtering and separating the radioactive slurry to obtain filter residue and filtrate;
the drying device is used for drying the filter residue in the filtering device to obtain dry filter residue;
the cement solidification device is used for carrying out cement solidification treatment on filtrate obtained by filtering in the filtering device;
and the sealing device is used for sealing the dry filter residue obtained after drying by the drying device.
7. The radioactive mud treatment system of claim 6, wherein the filter apparatus comprises a filter container, a vacuum device, and a first storage tank,
a feeding pipeline is arranged on the filtering container;
the vacuum equipment is communicated with the filtering container and is used for vacuumizing the interior of the filtering container;
the first storage tank is communicated with the filtering container and is used for receiving filtrate generated after filtering in the filtering container.
8. The radioactive mud treatment system according to claim 7, wherein a level meter is provided in the filtering container for measuring the height of the radioactive mud in the filtering container and sending an electrical signal when the measured height reaches a preset height threshold value;
and a feeding valve is arranged on the feeding pipeline, is electrically connected with the level meter and is used for controlling the feeding valve to be closed according to an electric signal sent by the level meter.
9. The radioactive mud treatment system according to claim 6, wherein the drying apparatus comprises an air inlet line in communication with the filter container and a first heater for heating the gas in the air inlet line to form a hot gas;
and/or the drying device comprises a second heater which is arranged outside the filtering container and used for heating the filtering container.
10. The radioactive slurry treatment system according to any one of claims 6 to 9, further comprising a condensing device,
the condensing device comprises a condenser and a second storage tank,
an inlet of the condenser is communicated with the filtering container and is used for cooling a gas mixture generated when the drying device dries the filter residue;
and the second storage tank is communicated with an outlet of the condenser and is used for receiving condensate obtained by cooling in the condenser.
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