CN112509723B - Radioactive mud treatment method and system - Google Patents
Radioactive mud treatment method and system Download PDFInfo
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- CN112509723B CN112509723B CN202011260392.7A CN202011260392A CN112509723B CN 112509723 B CN112509723 B CN 112509723B CN 202011260392 A CN202011260392 A CN 202011260392A CN 112509723 B CN112509723 B CN 112509723B
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- 230000002285 radioactive effect Effects 0.000 title claims abstract description 108
- 238000000034 method Methods 0.000 title claims abstract description 35
- 238000001035 drying Methods 0.000 claims abstract description 67
- 239000002002 slurry Substances 0.000 claims abstract description 54
- 239000000706 filtrate Substances 0.000 claims abstract description 45
- 239000004568 cement Substances 0.000 claims abstract description 42
- 239000007788 liquid Substances 0.000 claims abstract description 31
- 238000007789 sealing Methods 0.000 claims abstract description 26
- 238000000926 separation method Methods 0.000 claims abstract description 14
- 238000001914 filtration Methods 0.000 claims description 120
- 239000000203 mixture Substances 0.000 claims description 25
- 238000003860 storage Methods 0.000 claims description 24
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 18
- 238000010438 heat treatment Methods 0.000 claims description 14
- 238000001816 cooling Methods 0.000 claims description 9
- 239000011148 porous material Substances 0.000 claims description 7
- 238000003828 vacuum filtration Methods 0.000 claims description 7
- 238000004891 communication Methods 0.000 claims description 3
- 239000010802 sludge Substances 0.000 claims 1
- 230000000694 effects Effects 0.000 abstract description 9
- 239000007789 gas Substances 0.000 description 76
- 239000000126 substance Substances 0.000 description 16
- 230000005855 radiation Effects 0.000 description 14
- 239000007787 solid Substances 0.000 description 12
- 238000007711 solidification Methods 0.000 description 11
- 230000008023 solidification Effects 0.000 description 11
- 239000002699 waste material Substances 0.000 description 11
- 238000009835 boiling Methods 0.000 description 9
- 239000000941 radioactive substance Substances 0.000 description 7
- 239000002901 radioactive waste Substances 0.000 description 6
- 238000005406 washing Methods 0.000 description 6
- 239000002245 particle Substances 0.000 description 5
- 239000007790 solid phase Substances 0.000 description 4
- 229910000831 Steel Inorganic materials 0.000 description 3
- 238000009833 condensation Methods 0.000 description 3
- 230000005494 condensation Effects 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
- 238000005516 engineering process Methods 0.000 description 2
- 238000001704 evaporation Methods 0.000 description 2
- 230000008020 evaporation 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
- 230000007547 defect Effects 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000002927 high level radioactive waste Substances 0.000 description 1
- 238000002955 isolation Methods 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 238000002156 mixing Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000003672 processing method Methods 0.000 description 1
- 238000010926 purge Methods 0.000 description 1
- 239000013049 sediment Substances 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
Classifications
-
- 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
Landscapes
- 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 mud treatment method, which comprises the following steps: s1, carrying out solid-liquid separation on radioactive slurry to obtain filtrate and filter residues; s2, drying the filter residue to obtain dry filter residue; s3, performing sealing treatment on the dry filter residues; s4, performing cement curing treatment on the filtrate. The invention also discloses a radioactive slurry treatment system. The invention can solve the problem of the treatment of radioactive mud with higher content of alpha nuclide, 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 mud often appears in a large radioactive waste liquid storage tank, and the radioactive mud is characterized by containing a large amount of alpha nuclides, and the alpha nuclides are mainly distributed in solid-phase mud, the existing radioactive mud treatment modes such as cement solidification and the like are mainly used for treating low-level radioactive mud, the alpha nuclide has higher radioactivity level and cannot be directly treated by adopting the cement solidification and the like, and at present, domestic treatment of mud with higher alpha nuclide content and the like does not have mature engineering experience for reference.
Disclosure of Invention
Aiming at the defects existing 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 higher alpha nuclide content.
According to one aspect of the invention, a radioactive mud treatment method is provided, and the technical scheme is as follows:
a method of radioactive mud treatment comprising:
s1, carrying out solid-liquid separation on radioactive slurry to obtain separated filtrate and filter residues;
s2, drying the filter residue to obtain dry filter residue;
s3, performing sealing treatment on the dry filter residues;
s4, performing cement curing treatment on the filtrate.
Preferably, the method further comprises:
s5, condensing the gas mixture generated in the step S2 when the filter residues are subjected to drying treatment, and performing cement curing treatment on the generated condensate.
Preferably, in step S1, the radioactive mud is subjected to solid-liquid separation, in particular vacuum filtration using a filter bag,
the relative vacuum degree of vacuum filtration is 10-93 KPa, and the filter pore diameter of the filter bag is 10-500 μm.
Preferably, the drying treatment is to heat the filter residues by adopting hot gas, wherein the temperature of the hot gas is 90-110 ℃; and/or the number of the groups of groups,
the drying treatment is to heat filter residues by a heater, and 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%.
According to another aspect of the invention, a radioactive mud treatment system is provided, which has the following technical scheme:
a radioactive mud treatment system, comprising: a filtering device, a drying device, a cement curing device and a sealing device,
the filtering device is used for introducing radioactive slurry, and filtering and separating the radioactive slurry to obtain filter residues and filtrate;
the drying device is used for drying the filter residues in the filtering device to obtain dry filter residues;
the cement solidifying device is used for carrying out cement solidifying treatment on the filtrate obtained by filtering in the filtering device;
and the sealing device is used for sealing the dried filter residues obtained after the drying device is used for drying.
Preferably, the filtering device comprises a filtering container, a vacuum device and a first storage tank,
a feed pipeline is arranged on the filter container;
the vacuum equipment is communicated with the filter container and is used for vacuumizing the interior of the filter 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 gauge is arranged in the filtering container and is 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 in the filtering container;
the feeding pipeline is provided with a feeding valve, the feeding valve is electrically connected with the level meter and used for controlling the feeding valve to be closed according to an electric signal sent by the level meter.
Preferably, the drying means comprises an inlet line in communication with the filtration vessel and a first heater for heating the gas in the inlet line to form a hot gas;
and/or the drying device comprises a second heater, and the second heater is arranged outside the filtering container and is used for heating the filtering container.
Preferably, the system further comprises condensing means,
the condensing means comprises a condenser and a second storage tank,
the inlet of the condenser is communicated with the filtering container and is used for cooling the gas mixture generated when the filter residues are dried by the drying device;
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 mud treatment method and system have the following beneficial effects:
(1) The method can carry out solid-liquid separation on the radioactive mud, thereby reducing the solid content in the radioactive mud (filtrate), obtaining filter residues with high radioactivity level (the alpha nuclide activity concentration is about E+7Bq/Kg) and filtrate with low radioactivity level (the alpha nuclide activity concentration is less than or equal to E+5Bq/Kg), directly treating the filter residues by adopting modes such as cement solidification and the like, sealing and preserving the filter residues by adopting a special treatment barrel for radioactive wastes, and has good treatment effect, can solve the problem that the traditional technology cannot treat the high-level radioactive mud, and can be suitable for outlet engineering of the radioactive mud with higher 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 atmospheric pollution is reduced.
(3) The method is not limited by the radiation level of the radioactive mud, is suitable for all types of radioactive mud, can conveniently adopt remote control in the treatment process, and can avoid high radioactive radiation risks caused by manual short-distance operation.
Drawings
FIG. 1 is a schematic flow chart of a method for treating radioactive mud according to an embodiment of the present invention;
FIG. 2 is a schematic diagram of a radioactive mud treatment system according to an embodiment of the present invention.
Wherein, 1-filtering the container; 2-a vacuum device; 3-a first tank; 4-a feed line; 5-a third tank; 6-a feed valve; 7-a bypass line; 8-a discharge pipeline; 9-a discharge valve; 10-a cement curing device; 11-a buffer tank; 12-isolating valve; 13-tail gas treatment; 14-an intake line; 15-an intake valve; 16-a gas supply device; 17-an air outlet pipe line; 18-a fan; 19-a second heater; a 20-condenser; 21-a second tank; 22-a transfer pump; 23-a waste bin; 24-waste disposal warehouse.
Detailed Description
The following description of the embodiments of the present invention will be made more apparent, and the embodiments described in detail, but not necessarily all, in connection with the accompanying drawings. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to be within the scope of the 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, carrying out solid-liquid separation on radioactive slurry to obtain filtrate and filter residues;
s2, drying the filter residue to obtain dry filter residue;
s3, performing sealing treatment on the dry filter residues;
s4, performing cement curing 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 residues and filtrate;
the drying device is used for drying filter residues in the filtering device;
the cement solidifying device is used for carrying out cement solidifying treatment on the filtrate obtained by filtering the filtering device;
and the sealing device is used for sealing the dried filter residues obtained after the drying device is used for drying.
Example 1
As shown in fig. 1, this embodiment discloses a radioactive mud treatment method, which includes:
s1, carrying out solid-liquid separation on the radioactive slurry to obtain filtrate and filter residues.
The radioactive slurry has high-level alpha nuclide (the radioactive activity concentration of the alpha nuclide is more than or equal to E+5Bq/Kg) which 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 can be treated in a cement solidification mode and the like.
Specifically, the radioactive slurry is introduced into a filter bag (or a filter screen) in a filter container through a feed pipeline, and vacuum filtration is performed under the pushing of 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 the 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 size in the radioactive slurry are trapped in the filter bag, namely filter residues are formed. The alpha nuclide radioactivity in the filtrate in the embodiment is less than or equal to E+5Bq/Kg.
In this embodiment, the relative vacuum degree generated by vacuumizing the filtering container in the vacuum filtering process is preferably 10-93 KPa to achieve a better filtering effect. In this embodiment, the vacuum pump is used to vacuumize the filtering container, so that the maximum relative vacuum degree is not less than 80KPa, and the relative vacuum degree required to meet the above vacuum filtering requirement can be completely provided.
In this example, the pore size of the filter bag or filter mesh during the vacuum filtration process is 10 to 500. Mu.m. More preferably, the pore size of the filter bag or filter mesh can be 10-100 μm, and can be used for filtering the slurry with lower solid phase content (the volume percent of the solid phase is not more than 20% of the volume of the slurry); alternatively, the filter bags or screens can have a pore size of 100-500 μm and can be used to filter slurries with relatively high solids content (volume percent solids exceeding 20% of the slurry volume).
Considering that the radioactive slurry in this embodiment contains a large amount of alpha nuclide with high level radioactivity, in this embodiment, a level meter is arranged in the filtering container to carry out limit measurement on the height of the introduced radioactive slurry, and a feed valve linked with the level meter is arranged on a feed pipe line, so that automatic linkage control is carried out when the level meter detects that the height of the radioactive slurry in the filtering container reaches the limit height of the filtering container, 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 pipeline is closed by automatic linkage to complete feeding, so that the radioactive radiation risk existing in manual operation can be avoided.
In this embodiment, after feeding the radioactive mud into the filter vessel, it further comprises: the radioactive mud pipeline is washed, for example, tap water or other low-level radioactive clear liquid can be used for washing, and the washed water is introduced into the filtering container and filtered together with radioactive sediment.
S2, drying the filter residue to obtain dry filter residue.
In an alternative 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 water in the filter residue is evaporated into steam, and dry filter residue is obtained. The gas mixture of steam, hot gas and the like is discharged through an air outlet pipeline arranged on the filtering container, negative pressure is pumped at the air outlet pipeline side of the filtering container, and 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, compressed air is preferably adopted as the hot gas, and the flow rate of the compressed air is preferably 5-500L/min; the temperature of the hot gas is preferably 90 to 110 ℃.
In another alternative embodiment, the filter residue in the filtering container may be directly heated by a heater, so that the water in the filter residue is evaporated into steam, and dry filter residue is obtained. The gas mixture such as steam is discharged through the outlet pipe line arranged on the filtering container, and negative pressure is pumped at the outlet pipe line side of the filtering container, so that the steam generated by drying is rapidly discharged from the filtering container through the outlet pipe line under the pushing of the negative pressure. In this embodiment, the heating temperature of the heater is preferably 90 to 110 ℃.
Of course, two modes of hot gas introduction and direct heating can be adopted simultaneously, and filter residues can be dried simultaneously.
In this embodiment, the drying process for the filter residue obtained by filtration further includes: and detecting the humidity of the gas discharged from the gas outlet of the filtering container, and judging whether the filter residue is dried or not through the humidity detection, thereby determining the end point of the drying of the filter residue. In order to ensure that the filter residues are sufficiently dried, the moisture content of the dried filter residues in the embodiment should be less than 1%, and the humidity of the corresponding gas discharged from the gas outlet of the filtering container is 1-10%, and specifically can be selected according to different material compositions.
S3, performing sealing treatment on the dry filter residues.
S4, performing cement curing treatment on the filtrate.
Specifically, in step S3, the dry filter residue is transferred to a storage container capable of containing high-level radioactive waste, for example, the dry filter residue and the filter bag can be taken out from the filter container together by a manipulator, a crane or the like, and put into a steel waste barrel capable of resisting radioactive radiation, sealed by welding or the like, and transferred to a radioactive waste disposal warehouse for storage after barrelling, so that the filter residue treatment is completed. And S4, introducing filtrate obtained by solid-liquid separation into a cement curing device, mixing with cement to form a mixture, solidifying to form a cement curing body, and finishing filtrate treatment.
In addition to the evaporation of water, it is considered that, during the drying of the filter residue, some low-boiling substances with boiling points close to or lower than that of water may be volatilized into a gaseous state due to heat, that is, the gas generated by the drying process of the filter container includes steam, gaseous low-boiling substances and gas introduced during the drying process, and these gases are collectively referred to as a gas mixture, and some low-boiling radioactive substances may be contained in the gas mixture, so that the gas mixture may be directly discharged to cause atmospheric pollution. Therefore, the processing method in this embodiment further includes:
s5, condensing the gas mixture generated by the drying treatment, and performing cement curing treatment on the condensate.
Specifically, the gas mixture containing steam generated in the drying process is introduced into a condenser for cooling and condensing, the cooling temperature of the condenser is preferably 20-25 ℃, so that steam in the gas mixture and other low-boiling-point substances with the same or similar boiling points as water are condensed into liquid, condensate obtained by condensation is introduced into a cement solidification device and mixed with cement to form a mixture, and the mixture is solidified into a cement solidified body after solidification, so that filtrate treatment is completed. The uncondensed gas discharged by the condenser is introduced into a tail gas treatment procedure, for example, the uncondensed gas can be firstly introduced into a washing tower for washing and then is preheated, then the uncondensed gas is introduced into a tail gas filtering unit for filtering treatment, harmful substances such as radioactive substances in the tail gas are further removed, and the treated tail gas is sent to an exhaust center of a nuclear power plant to finish treatment and discharge.
According to the method for treating the radioactive mud, the solid-liquid separation treatment is carried out on the radioactive mud to obtain the solid radiation with high level and the liquid radiation with low level, the separated solid radiation is dried, the gas mixture generated by drying is condensed, the dried solid radiation with high level is hermetically stored by a waste bin specially used for containing radioactive wastes, and the liquid radiation with low level and condensate generated by condensation are directly treated by adopting the cement solidification and other modes, so that the problem that the prior art cannot treat the high-level radioactive mud with high content of alpha nuclide is solved, meanwhile, the method is also suitable for treating the low-level radioactive mud, the treatment effect of the low-level radioactive mud can be further improved, namely the method is not limited by the radioactivity level of the mud, is suitable for all types of radioactive mud, the treatment process can be conveniently controlled by remote control, and the high-radioactive radiation risk caused by manual short-distance operation can be avoided.
Example 2
As shown in fig. 2, the present embodiment discloses a radioactive slurry treatment system, which includes a filtering device, a drying device, a cement curing device, and a sealing device, wherein: the filtering device is used for introducing the radioactive slurry and filtering the radioactive slurry to obtain filter residues and filtrate; the drying device is used for drying the filter residues in the filtering device to obtain dry filter residues; the cement solidifying device is used for carrying out cement solidifying treatment on the filtrate obtained in the filtering device; and the sealing device is used for sealing the dry filter residues obtained in the drying device.
Specifically, the filtering device comprises a filtering container 1, a vacuum apparatus 2 and a first tank 3. The filter vessel 1 is provided with a feed line 4, preferably at the top of the filter vessel 1, for feeding radioactive mud into the filter vessel 1. A third tank 5 may be provided upstream of the feed line 4 to temporarily store the radioactive mud. Downstream of the feed line 4 is a feed valve 6 to control the feeding of radioactive mud into the filter vessel 1. A feed pump may also be provided on the feed line 4 to deliver radioactive mud. In this embodiment, the feeding line 4 may further be provided with a bypass line 7 connected thereto, and the bypass line 7 is filled with production water, such as tap water, for flushing the feeding line 4 and the feeding valve 6 with water after the feeding of the feeding line 4 is completed, and the flushing water enters the filtering container 1 to be filtered together with the radioactive slurry introduced, and the bypass line 7 is closed after the flushing is completed. The filter container 1 is internally provided with a filter bag (or a filter screen), the introduced radioactive slurry enters the filter bag, the filtrate is filtered out from the filter bag, and most of solid particles containing alpha nuclide are trapped in the filter bag, namely filter residues, so that the radiation level of the radioactive slurry in the filtrate is reduced, and the subsequent cement solidification treatment is facilitated. In this embodiment, the pore diameter of the filter bag is preferably 10-500 μm, and the proper pore diameter of the filter bag can be selected to meet the filtration requirement and properly improve the filtration efficiency. 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, the level meter is further disposed in the filtering container 1, and is electrically connected with the feeding valve 6 by adopting linkage control, that is, the level meter is used for limiting and measuring the height of the radioactive slurry introduced into the filtering container, a limiting height threshold value of the radioactive slurry introduced into the filtering container is set on the level meter, an electric signal is sent when the height value measured by the level meter reaches the height threshold value preset in the filtering container, the feeding valve 6 controls the feeding valve to be automatically closed when receiving the electric signal sent by the level meter, automatic feeding of the radioactive slurry is completed, and the risk of radioactive irradiation caused by close-range operation of staff can be avoided.
The bottom or the lower part of the filtering container 1 is provided with a liquid outlet, the first storage tank 3 is communicated with the liquid outlet of the filtering container 1 through a discharge pipeline 8, a discharge valve 9 is arranged on the discharge pipeline 8 to control the opening and closing of the discharge pipeline 8, filtrate generated by filtering is discharged, and the first storage tank 3 is used for receiving and temporarily storing the filtrate. The vacuum equipment is communicated with the filtering container 1 and is used for vacuumizing the inside of the filtering container 1 so as to provide the relative vacuum degree required by the radioactive slurry filtering and promote the filtering effect of the filter screen, namely, the vacuum filtering is carried out. The relative vacuum degree generated by the vacuum device for vacuumizing the filter container 1 is preferably 10-93 KPa so as to ensure good filtering effect.
In this embodiment, the vacuum apparatus 2 may employ a vacuum pump, where 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 filtration vessel 1 through the first storage tank 3, and the vacuum pump is used to vacuum-filter the radioactive slurry in the filtration vessel 1, so as to implement rapid filtration, and the filtered filtrate flows into the first storage tank 3 for temporary storage. The liquid outlet of the first storage tank 3 is connected to a cement solidification device 10 for carrying out cement solidification treatment on filtrate generated by filtration. A buffer tank 11 and an isolation valve 12 are also provided between the vacuum pump and the first tank 3 to prevent back suction of filtrate to the vacuum pump. The gas outlet of the vacuum pump is connected with the tail gas treatment process 13 to avoid pollution caused by direct entry of harmful gases such as radioactive substances into the atmosphere.
In some alternative embodiments, the drying device in this example comprises an inlet line 14, the outlet of which inlet line 14 communicates with the filter vessel 1, and a first heater for heating the gas in the inlet line 14 to form hot gas. Specifically, the outlet of the air inlet line 14 may be connected to the liquid outlet of the filtering container 1 or connected to the discharge line 8 connected to the liquid outlet, as shown in fig. 2, the air inlet line 14 is provided with an air inlet valve 15, and the air inlet valve 15 is closed to open the discharge valve 9 during filtering; at the time of drying, the inlet valve 15 is opened by closing the inlet valve 9. The inlet of the air inlet line 14 is used for communicating with the air supply device 16, and the first heater (not shown in the figure) is arranged at the upstream of the air inlet line, for example, the first heater can be arranged between the air supply device 16 and the air inlet valve, or electric tracing is arranged on the air inlet line as the first heater, and is used for heating the air supplied by the air supply device 16, the heated air is introduced into the filter container 1, and heat exchange is performed on the filter residues in the filter container 1, so that water in the filter residues is evaporated into steam, and dry filter residues are obtained. The filtering container 1 is 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 pump negative pressure, so that the steam is rapidly discharged from the filtering container 1 through the air outlet pipeline 17 under the pushing of the negative pressure. In this embodiment, the air supply device 16 may employ a compressor, the air is compressed air, and the flow rate of the compressed air is preferably 5-500L/min; the first heater may be a commercially available heater such as an electric heater or an electromagnetic heater, and the temperature of the heated gas (compressed air) is preferably 90 to 110 ℃. After the drying is finished, cold or normal-temperature gas (compressed air) is introduced into the filtering container 1 by only starting the gas supply device 16 (air compressor), so that the dry filter residues are rapidly cooled, for example, cooled to the room temperature, and the system treatment efficiency is improved.
In another alternative embodiment, the drying device in this example comprises a second heater 19. The second heater 19 is sleeved outside the filtering container 1 and is 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 the condensing device so as to discharge the 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 pump negative pressure, so that the steam is rapidly discharged from the filtering container 1 through the air outlet pipeline 17 under the pushing of the negative pressure. In the present embodiment, the second heater 19 may be an electric heater or an electromagnetic heater, and the heating temperature is preferably 90-110deg.C
Of course, the drying device of this embodiment may also adopt the two drying devices to dry, and adopt the mode of simultaneously carrying out the hot gas introduction and the direct heating to dry the filter residue, that is, the drying device includes the air inlet line 14, the first heater, the second heater 19 and other devices, and the specific connection mode thereof is as described above, and will not be described herein.
In this embodiment, the air outlet line 17 may be provided with a humidity detector, so as to determine the drying end point by determining the degree of drying the filter residues according to the humidity of the air discharged from the filter container 1 during the drying process.
Specifically, the sealing device of the present embodiment includes a waste bin 23 and a transfer device. The waste drum can be a special waste drum for radioactive waste, such as a steel drum resistant to high-level radioactive radiation, and is used for sealing and preserving dry filter residues in a welding mode. The transferring equipment can adopt a mechanical arm, a crane and the like, is used for taking out the dry filter residues in the filter container 1, pointing the dry filter residues into the waste barrel 23 for sealing and storing, and transferring the filter residues into the waste disposal warehouse 24 for storing after barreling the filter residues, so as to finish the filter residue treatment.
In the process of drying the filter residue, in addition to the evaporation of water, some low-boiling substances having a boiling point close to or lower than that of water may be volatilized into a gaseous state by heating, that is, the gas discharged from the gas outlet line 17 in the filter vessel 1 includes steam, the gaseous low-boiling substances, and the gas introduced during the drying process, and the gas in the gas outlet line 17 is generally referred to as a gas mixture, and the direct discharge of the gas mixture may cause atmospheric pollution. Therefore, the radioactive mud 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 the low-boiling substances therein into liquid, so as to reduce the content of harmful substances such as radioactive substances contained in the uncondensed gas and reduce the atmospheric pollution.
Specifically, the condensing means comprises a condenser 20 and a second tank 21. The inlet of the condenser 20 communicates with the filter vessel 1 via an outlet line 17 for introducing 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 the steam and low-boiling-point substances in the gas mixture are quickly condensed into liquid, condensate is obtained, and the condensate is discharged through a liquid outlet on the condenser 20. The cooling medium in the condenser 20 of the present embodiment may 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 condensate obtained by cooling the condenser 20 and temporary storage. The second tank 21 is also in communication with the cement curing device 10, and the condensate in the second tank 21 can be delivered to the cement curing device 10 for cement curing treatment by providing a delivery pump 22. 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, the uncondensed gas in the condenser 20 is discharged through the gas outlet of the condenser 20, enters the washing tower for washing, enters the preheater for preheating and the like, is then introduced into a tail gas filtering unit for filtering treatment, harmful substances such as radioactive substances and the like in the tail gas are further removed, and the treated tail gas is sent to a nuclear power plant exhaust center for treatment and discharge.
The radioactive mud treatment system of the embodiment has the following beneficial effects:
(1) The method can carry out solid-liquid separation on the radioactive mud, thereby reducing the solid content in the radioactive mud (filtrate), obtaining high-level radioactive filter residues and low-level radioactive filtrate, wherein the filtrate can be directly treated in a cement solidification mode and the like, the filter residues are hermetically stored in a special treatment barrel for radioactive wastes, the treatment effect is good, the problem that the high-level radioactive mud cannot be treated by the traditional technology can be solved, and the method is applicable to outlet engineering of the radioactive mud with higher 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 atmospheric pollution is reduced.
Example 3
The embodiment discloses a radioactive slurry treatment method, which adopts the treatment system of the embodiment 2 to treat radioactive slurry with higher alpha nuclide content, and comprises the following specific steps:
(1) The sealing cover of the filter container 1 is opened, the filter bag with the aperture of 500 mu m is arranged in the filter container 1 by the cooperation of a mechanical arm, a crane and other devices, and the sealing cover is reset and sealed.
(2) The feeding valve 6 is opened, the radioactive slurry in the third storage tank 5 is introduced into the filter bag in the filter container 1 at a flow rate of 20-50L/min, and when the level meter detects that the introduced radioactive slurry reaches the set limit height, the feeding valve 6 is closed in a linkage way.
(3) The bypass line 7 is opened and the feed line 4 is flushed with purge water.
(4) The vacuum pump 2 is started to pump negative pressure to the filter container 1, so that the radioactive slurry in the filter bag is filtered under the action of the negative pressure, the filtrate flows into the first storage tank 3, and the filter residues are remained in the filter bag, namely, the solid-liquid separation process.
(5) After the solid-liquid separation is completed, the vacuum pump is closed, the drying device is opened, for example, an air inlet pipeline and the first heater are opened, compressed air at 90-110 ℃ is introduced at the flow rate of 100-200L/min, and/or the second heater is opened to heat the filter container to 90-110 ℃ so that the water in the filter residue is evaporated into steam, namely, the drying process.
(6) Simultaneously, the fan 18 is turned on, and the gas mixture of steam, introduced compressed air and the like is discharged into the condenser 20 through the gas outlet pipeline 17 for cooling, so that the steam and low-boiling-point substances in the gas are condensed into liquid, and condensate is obtained, namely, the condensation process. The condensate is discharged to a second storage tank 21 for temporary storage, and the uncondensed gas is conveyed to a tail gas treatment process 13 for tail gas treatment through a fan 18. When it is detected that the humidity of the gas in the gas outlet line 17 is less than a certain value (e.g., the humidity is 5%, which can be obtained by a test according to the composition of the gas), the drying device is turned off.
(7) After the drying and condensing process is finished, the sealing cover of the filtering container 1 is opened, the filter residues and the filter bags are together transferred to a waste barrel 23 (such as a 200L steel barrel) for sealing through the cooperation of a mechanical arm or a crane and the like, and the filter residues and the filter bags are transferred to a waste disposal warehouse 24 for storage, so that the treatment of the solid radiation with high radiation level is finished.
(8) The filtrate in the first tank 3 and the condensate in the second tank 21 are fed to the cement curing device 10, and mixed with cement or the like to form a cement cured body, whereby the filtrate and condensate treatment at a low radioactivity level is completed.
It is to be understood that the above embodiments are merely illustrative of the application of the principles of the present invention, but not in limitation thereof. Various modifications and improvements may be made by those skilled in the art without departing from the spirit and substance of the invention, and are also considered to be within the scope of the invention.
Claims (9)
1. A method of radioactive mud treatment comprising:
s1, carrying out solid-liquid separation on radioactive slurry with the alpha nuclide radioactivity concentration of more than or equal to E+5Bq/Kg to obtain separated filtrate and filter residues, wherein the solid-liquid separation is carried out by adopting a filter bag for vacuum filtration, the relative vacuum degree of the vacuum filtration is 10-93 KPa, the filtration pore diameter of the filter bag is 10-500 mu m, and the alpha nuclide radioactivity in the filtrate is less than or equal to E+5Bq/Kg;
s2, drying the filter residue to obtain dry filter residue;
s3, performing sealing treatment on the dry filter residues;
s4, performing cement curing treatment on the filtrate.
2. The radioactive mud treatment method according to claim 1, further comprising:
s5, condensing the gas mixture generated in the step S2 when the filter residues are subjected to drying treatment, and performing cement curing treatment on the generated condensate.
3. The method for treating radioactive mud according to any one of claims 1 to 2, wherein the drying treatment is to heat the filter residue with a hot gas having a temperature of 90 to 110 ℃; and/or the number of the groups of groups,
the drying treatment is to heat filter residues by a heater, and the heating temperature of the heater is 90-110 ℃.
4. The method for treating radioactive sludge according to any one of claims 1 to 2, wherein the water content of the dry filter residue is not more than 1%.
5. A radioactive mud treatment system, comprising: a filtering device, a drying device, a cement curing device and a sealing device,
the filtering device is used for introducing radioactive slurry with the alpha nuclide radioactivity concentration of more than or equal to E+5Bq/Kg, filtering and separating the radioactive slurry to obtain filter residues and filtrate, the filtering device comprises a filtering container and vacuum equipment, wherein a filter bag is arranged in the filtering container, the aperture of the filter bag is 10-500 mu m, the vacuum equipment is communicated with the filtering container and is used for vacuumizing the filtering container, the relative vacuum degree generated by vacuumizing the filtering container is 10-93 KP, and the radioactive slurry in the filtering container is subjected to vacuum filtration to obtain filtrate with the alpha nuclide radioactivity of less than or equal to E+5Bq/Kg;
the drying device is used for drying the filter residues in the filtering device to obtain dry filter residues;
the cement solidifying device is used for carrying out cement solidifying treatment on the filtrate obtained by filtering in the filtering device;
and the sealing device is used for sealing the dried filter residues obtained after the drying device is used for drying.
6. The radioactive slurry treatment system of claim 5, wherein the filtering device further comprises a first reservoir,
a feed pipeline is arranged on the filter container;
the first storage tank is communicated with the filtering container and is used for receiving filtrate generated after filtering in the filtering container.
7. The radioactive mud treatment system according to claim 6, wherein a level gauge is provided in the filtering container for measuring the height of the radioactive mud in the filtering container and transmitting an electrical signal when the measured height value reaches a height threshold preset therein;
the feeding pipeline is provided with a feeding valve, the feeding valve is electrically connected with the level meter and used for controlling the feeding valve to be closed according to an electric signal sent by the level meter.
8. The radioactive mud treatment system of claim 5, wherein the drying apparatus comprises an inlet line in communication with the filter vessel and a first heater for heating the gas in the inlet line to form a hot gas;
and/or the drying device comprises a second heater, and the second heater is arranged outside the filtering container and is used for heating the filtering container.
9. The radioactive slurry treatment system according to any one of claims 5 to 8, further comprising a condensing device,
the condensing means comprises a condenser and a second storage tank,
the inlet of the condenser is communicated with the filtering container and is used for cooling the gas mixture generated when the filter residues are dried by the drying device;
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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