CN115831424A - Method and system for treating radioactive waste liquid - Google Patents
Method and system for treating radioactive waste liquid Download PDFInfo
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- CN115831424A CN115831424A CN202211537898.7A CN202211537898A CN115831424A CN 115831424 A CN115831424 A CN 115831424A CN 202211537898 A CN202211537898 A CN 202211537898A CN 115831424 A CN115831424 A CN 115831424A
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- 239000007788 liquid Substances 0.000 title claims abstract description 180
- 239000002901 radioactive waste Substances 0.000 title claims abstract description 147
- 238000000034 method Methods 0.000 title claims abstract description 51
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 222
- 239000013078 crystal Substances 0.000 claims abstract description 164
- 239000006228 supernatant Substances 0.000 claims abstract description 139
- 238000007710 freezing Methods 0.000 claims abstract description 77
- 230000008014 freezing Effects 0.000 claims abstract description 76
- 238000001816 cooling Methods 0.000 claims abstract description 72
- 238000001556 precipitation Methods 0.000 claims abstract description 64
- 238000005189 flocculation Methods 0.000 claims abstract description 61
- 230000016615 flocculation Effects 0.000 claims abstract description 60
- 230000008018 melting Effects 0.000 claims description 24
- 238000002844 melting Methods 0.000 claims description 24
- 230000002285 radioactive effect Effects 0.000 claims description 20
- 239000010808 liquid waste Substances 0.000 claims description 15
- 239000012141 concentrate Substances 0.000 claims description 13
- 239000008394 flocculating agent Substances 0.000 claims description 7
- 229910019142 PO4 Inorganic materials 0.000 claims description 5
- NBIIXXVUZAFLBC-UHFFFAOYSA-K phosphate Chemical compound [O-]P([O-])([O-])=O NBIIXXVUZAFLBC-UHFFFAOYSA-K 0.000 claims description 5
- 239000010452 phosphate Substances 0.000 claims description 5
- 238000007599 discharging Methods 0.000 claims description 4
- 238000000926 separation method Methods 0.000 claims description 4
- AZDRQVAHHNSJOQ-UHFFFAOYSA-N alumane Chemical class [AlH3] AZDRQVAHHNSJOQ-UHFFFAOYSA-N 0.000 claims description 3
- 150000002696 manganese Chemical class 0.000 claims description 3
- 150000002505 iron Chemical class 0.000 claims description 2
- 230000003311 flocculating effect Effects 0.000 claims 1
- 239000000126 substance Substances 0.000 claims 1
- 239000012535 impurity Substances 0.000 description 15
- 238000005086 pumping Methods 0.000 description 14
- 239000000941 radioactive substance Substances 0.000 description 13
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- 238000005265 energy consumption Methods 0.000 description 10
- 239000002699 waste material Substances 0.000 description 6
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- 238000004062 sedimentation Methods 0.000 description 5
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- 239000011550 stock solution Substances 0.000 description 5
- 239000004254 Ammonium phosphate Substances 0.000 description 4
- 229910000148 ammonium phosphate Inorganic materials 0.000 description 4
- 235000019289 ammonium phosphates Nutrition 0.000 description 4
- 230000006378 damage Effects 0.000 description 4
- 238000010586 diagram Methods 0.000 description 4
- MNNHAPBLZZVQHP-UHFFFAOYSA-N diammonium hydrogen phosphate Chemical compound [NH4+].[NH4+].OP([O-])([O-])=O MNNHAPBLZZVQHP-UHFFFAOYSA-N 0.000 description 4
- 230000000694 effects Effects 0.000 description 4
- 238000001704 evaporation Methods 0.000 description 4
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- 239000003153 chemical reaction reagent Substances 0.000 description 3
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- 238000005406 washing Methods 0.000 description 3
- 239000002351 wastewater Substances 0.000 description 3
- VEXZGXHMUGYJMC-UHFFFAOYSA-M Chloride anion Chemical compound [Cl-] VEXZGXHMUGYJMC-UHFFFAOYSA-M 0.000 description 2
- 230000008878 coupling Effects 0.000 description 2
- 238000010168 coupling process Methods 0.000 description 2
- 238000005859 coupling reaction Methods 0.000 description 2
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- XLYOFNOQVPJJNP-UHFFFAOYSA-M hydroxide Chemical compound [OH-] XLYOFNOQVPJJNP-UHFFFAOYSA-M 0.000 description 2
- 230000007774 longterm Effects 0.000 description 2
- PWHULOQIROXLJO-UHFFFAOYSA-N Manganese Chemical compound [Mn] PWHULOQIROXLJO-UHFFFAOYSA-N 0.000 description 1
- 229910021380 Manganese Chloride Inorganic materials 0.000 description 1
- GLFNIEUTAYBVOC-UHFFFAOYSA-L Manganese chloride Chemical compound Cl[Mn]Cl GLFNIEUTAYBVOC-UHFFFAOYSA-L 0.000 description 1
- QAOWNCQODCNURD-UHFFFAOYSA-L Sulfate Chemical compound [O-]S([O-])(=O)=O QAOWNCQODCNURD-UHFFFAOYSA-L 0.000 description 1
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- RBTARNINKXHZNM-UHFFFAOYSA-K iron trichloride Chemical compound Cl[Fe](Cl)Cl RBTARNINKXHZNM-UHFFFAOYSA-K 0.000 description 1
- BAUYGSIQEAFULO-UHFFFAOYSA-L iron(2+) sulfate (anhydrous) Chemical compound [Fe+2].[O-]S([O-])(=O)=O BAUYGSIQEAFULO-UHFFFAOYSA-L 0.000 description 1
- RUTXIHLAWFEWGM-UHFFFAOYSA-H iron(3+) sulfate Chemical compound [Fe+3].[Fe+3].[O-]S([O-])(=O)=O.[O-]S([O-])(=O)=O.[O-]S([O-])(=O)=O RUTXIHLAWFEWGM-UHFFFAOYSA-H 0.000 description 1
- 229910000359 iron(II) sulfate Inorganic materials 0.000 description 1
- 229910000360 iron(III) sulfate Inorganic materials 0.000 description 1
- 229910052748 manganese Inorganic materials 0.000 description 1
- 239000011572 manganese Substances 0.000 description 1
- 235000002867 manganese chloride Nutrition 0.000 description 1
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- 229940099607 manganese chloride Drugs 0.000 description 1
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- 235000007079 manganese sulphate Nutrition 0.000 description 1
- 239000011702 manganese sulphate Substances 0.000 description 1
- SQQMAOCOWKFBNP-UHFFFAOYSA-L manganese(II) sulfate Chemical compound [Mn+2].[O-]S([O-])(=O)=O SQQMAOCOWKFBNP-UHFFFAOYSA-L 0.000 description 1
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Abstract
Embodiments of the present application provide a method of treating radioactive waste. The method comprises the following steps: performing flocculation precipitation treatment on the radioactive waste liquid to obtain supernatant after precipitation; pre-cooling the supernatant; freezing and concentrating the pre-cooled supernatant to freeze at least part of water in the supernatant to form ice crystals, and concentrating the residual liquid to form concentrated radioactive waste liquid, wherein the cold energy of the freezing and concentrating treatment comes from natural cold energy in the environment; separating ice crystals and concentrating the radioactive waste liquid. Embodiments of the present application also provide a system for treating radioactive waste.
Description
Technical Field
The application relates to the technical field of radioactive waste liquid treatment, in particular to a method and a system for treating radioactive waste liquid.
Background
The radioactive waste liquid is liquid waste containing radioactive nuclide generated in the processes of nuclear facility operation and decommissioning, plant site decontamination and the like. With the rapid development of nuclear power technology, the amount of radioactive waste liquid is increasing day by day, and the treatment is urgently needed. Although the current treatment technologies are mature and can effectively treat the radioactive waste liquid, the treatment technologies may have the problems of high operation cost, high energy consumption, easy corrosion of equipment and the like. For example, the most used treatment method is flocculation precipitation-evaporative concentration-ion exchange coupling treatment method, wherein the main function is evaporative concentration, but the method consumes a large amount of energy during long-term operation and influences the service life of equipment during evaporation.
Disclosure of Invention
In view of the above, the present application is proposed to provide a method and system for treating radioactive liquid waste that overcomes or at least partially solves the above mentioned problems.
According to a first aspect of embodiments of the present application, there is provided a method of treating radioactive waste comprising: performing flocculation precipitation treatment on the radioactive waste liquid to obtain supernatant after precipitation; pre-cooling the supernatant; freezing and concentrating the pre-cooled supernatant to freeze at least part of water in the supernatant to form ice crystals, and concentrating the residual liquid to form concentrated radioactive waste liquid, wherein the cold energy of the freezing and concentrating treatment comes from natural cold energy in the environment; separating ice crystals and concentrating the radioactive waste liquid.
According to a second aspect of embodiments of the present application, there is provided a system for treating radioactive waste. The system adopts the radioactive liquid waste treatment method in the embodiment to realize the treatment of the radioactive liquid waste, and the system comprises: the raw liquid tank is used for storing radioactive waste liquid; the flocculation precipitation tank is connected with the raw liquid tank and is used for receiving the radioactive waste liquid and carrying out flocculation precipitation treatment on the radioactive waste liquid so as to obtain supernatant after precipitation; the pre-cooling tank is connected with the flocculation precipitation tank and is used for receiving the supernatant and pre-cooling the supernatant; the freezing concentration tank is connected with the precooling tank and is used for receiving the precooled supernatant and carrying out freezing concentration treatment on the precooled supernatant so as to freeze at least part of water in the supernatant to form ice crystals and concentrate the residual liquid to form concentrated radioactive waste liquid; wherein, the cold energy used by the freezing concentration tank comes from the natural cold energy in the environment.
The method for treating the radioactive waste liquid provided by the embodiment of the application is used for preliminarily removing impurities in the radioactive waste liquid by performing flocculation precipitation treatment on the radioactive waste liquid to obtain supernatant after precipitation, so that the influence of the impurities in the radioactive waste liquid on the subsequent freezing concentration treatment effect is reduced. And then precooling the supernatant to reduce the temperature of the supernatant and reduce the temperature difference between the supernatant and the subsequent freeze concentration treatment by adopting natural cold energy. And then, freezing and concentrating the pre-cooled supernatant to freeze at least part of water in the supernatant to form ice crystals, and concentrating the residual liquid to form concentrated radioactive waste liquid, so that the concentration of radioactive substances in the waste liquid is increased, the volume of the waste liquid is greatly reduced, and the subsequent treatment of the radioactive waste liquid is facilitated. In addition, the efficiency of treating the radioactive waste liquid can be effectively improved by pre-cooling treatment and then freezing concentration treatment, the energy consumption can be effectively reduced by adopting natural cold energy for freezing concentration, and the energy conservation and environmental protection are realized.
The system for treating the radioactive waste liquid provided by the embodiment of the application can realize enrichment of the radioactive nuclide in the radioactive waste liquid by utilizing natural cold energy in the environment, effectively reduces the energy consumption, and is more simplified in system composition. The method for treating radioactive liquid waste provided by the embodiment of the application can be applied to the system for treating radioactive liquid waste provided by the embodiment of the application.
Drawings
The above and/or additional aspects and advantages of the present invention will become apparent and readily appreciated from the following description of the embodiments, taken in conjunction with the accompanying drawings of which:
FIG. 1 is a schematic flow diagram of a method of treating radioactive waste according to one embodiment of the present application;
fig. 2 is a schematic diagram of a configuration of a system for treating radioactive waste according to one embodiment of the present application.
It is noted that the drawings are not necessarily to scale and are merely illustrative in nature and not intended to obscure the reader.
[ description of reference ]
1-raw liquid tank, 2-flocculation precipitation tank, 3-pre-cooling tank, 4-freezing concentration tank, 5-ice crystal storage tank, 6-concentrated liquid storage tank, 7-filter screen, 8-heat exchanger and 9-conveying device.
Detailed Description
In order to make the objects, technical solutions and advantages of the present application more clear, the technical solutions of the present application will be described below in detail and completely with reference to the accompanying drawings of the embodiments of the present application. It should be apparent that the described embodiment is one embodiment of the present application and not all embodiments. All other embodiments, which can be derived by a person skilled in the art from the described embodiments of the application without inventive effort, are within the scope of protection of the application.
It is to be noted that, unless otherwise defined, technical or scientific terms used herein shall have the ordinary meaning as understood by those of ordinary skill in the art to which this application belongs. If the description "first", "second", etc. is referred to throughout, the description of "first", "second", etc. is used only for distinguishing similar objects, and is not to be construed as indicating or implying a relative importance, order or number of technical features indicated, it being understood that the data described in "first", "second", etc. may be interchanged where appropriate. If "and/or" is presented throughout, it is meant to include three juxtapositions, exemplified by "A and/or B" and including either scheme A, or scheme B, or schemes in which both A and B are satisfied.
Fig. 1 is a schematic flow diagram of a method of treating radioactive waste according to one embodiment of the present application.
As shown in fig. 1, an embodiment of the present application first provides a method of treating radioactive waste, including: operation S101 to operation S104.
Operation S101 is performed to perform flocculation and precipitation treatment on the radioactive waste liquid, and obtain a supernatant after precipitation.
In operation S102, the supernatant is pre-cooled.
Operation S103, performing a freeze concentration process on the pre-cooled supernatant to freeze at least a portion of the water in the supernatant to form ice crystals, and concentrating the remaining liquid to form a concentrated radioactive waste liquid. Wherein, the cold energy of the freeze concentration treatment comes from the natural cold energy in the environment.
Operation S104, separating the ice crystals and concentrating the radioactive waste.
By adopting the method for treating the radioactive waste liquid provided by the embodiment of the application, the radioactive waste liquid is subjected to flocculation precipitation firstly to remove impurities in the radioactive waste liquid and reduce the influence of the impurities in the radioactive waste liquid on the subsequent freezing concentration treatment effect. And then precooling the supernatant obtained after the flocculation precipitation, reducing the temperature of the supernatant, and reducing the temperature difference between the supernatant and the subsequent freeze concentration treatment by adopting natural cold energy. And then, freezing and concentrating the pre-cooled supernatant to freeze at least part of water in the supernatant to form ice crystals, and concentrating the residual liquid to form concentrated radioactive waste liquid, so that the concentration of radioactive substances in the waste liquid is increased, the volume of the waste liquid is greatly reduced, and the concentrated radioactive waste liquid is conveniently subjected to subsequent treatment. Meanwhile, the crystal of the ice crystal obtained after the freezing concentration treatment is purer and more complete, and radioactive substances contained in the ice crystal are reduced. In addition, according to the embodiment, pre-cooling treatment is performed before freeze concentration treatment, so that the treatment efficiency and treatment effect of the radioactive waste liquid can be effectively improved.
In addition, the treatment method in the embodiment of the application adopts natural cold energy to carry out freezing concentration, so that the energy consumption can be effectively reduced, the treatment method is more environment-friendly, and the damage to equipment is less. Specifically, the supernatant may be placed in an environment with a low natural temperature, and the supernatant may be subjected to freeze concentration in a natural low-temperature environment.
In northern areas and high latitude areas, the outdoor temperature is lower in winter, and the characteristics of a large low-temperature storage place are possessed, so that the natural cold energy in the natural environment can be utilized to freeze and freeze the radioactive waste liquid naturally, the enrichment of the radioactive waste liquid is realized, and the energy consumption is reduced. In addition, compared with the existing evaporation concentration treatment method, the radioactive waste liquid treatment method based on natural cold energy has the advantages of lower energy consumption, remarkable operation cost saving and lower equipment requirement.
In some embodiments, in operation S101, the flocculation precipitation treatment comprises: one or more flocculating agents are added into radioactive waste water to realize the flocculation and precipitation of impurities in the radioactive waste water, reduce the existence of the impurities and reduce the influence of the impurities on the subsequent freezing and concentrating treatment.
In some embodiments, the radioactive waste stream can be flocculated by at least one of hydroxide precipitation, phosphate precipitation, and manganese flocculation. The flocculant used in this embodiment may be at least one of hydroxide, aluminum salt, iron salt, phosphate, and manganese salt. Wherein the aluminum salt can be selected from polyaluminum chloride, polyaluminum sulfate, polyaluminum phosphate, etc.; the ferric salt can be selected from polymeric ferric sulfate, ferric trichloride, ferrous sulfate, etc.; the phosphate can be selected from ammonium phosphate; manganese salt can be selected from manganese chloride and manganese sulfate. In some embodiments, natural polymer modified polyacrylamide and other materials can be used as the flocculant.
In some embodiments, the radioactive waste liquid may be subjected to a flocculation treatment using a flocculation settling tank. Specifically, the radioactive waste liquid is placed in a flocculation precipitation tank, and then a flocculating agent is added into the flocculation precipitation tank to flocculate and precipitate impurities in the radioactive waste liquid.
In operation S102, the supernatant may be pre-cooled using natural cold energy. Specifically, the supernatant may be placed in a natural low temperature environment, such as a winter outdoor environment in northern areas or high latitude areas. In northern areas and high latitude areas, the outdoor temperature is lower in winter, and the storage place has higher low temperature, so that the radioactive waste water can be naturally frozen and frozen by utilizing the natural cold energy in the natural environment, the enrichment of the radioactive waste liquid is realized, and the energy consumption is reduced. In addition, compared with the existing evaporation concentration treatment method, the radioactive waste liquid treatment method based on natural cold energy has the advantages of lower energy consumption, remarkable operation cost saving and lower equipment requirement.
In some embodiments, the supernatant may be pre-cooled using a pre-cooling tank. In particular, the supernatant formed after precipitation may be transferred to a pre-cooling tank for pre-cooling in the pre-cooling tank. For example, the supernatant in the flocculation precipitation tank may be transferred to a pre-cooling tank using a radioactive waste liquid transfer device. Wherein, the radioactive waste liquid conveying device can be a pump.
Further, after the ice crystals are formed, the supernatant can be pre-cooled by using water after the ice crystals are melted. In this embodiment, the water formed after the ice crystals are melted is used as cold energy for pre-cooling treatment of the supernatant, so that the energy consumption in the pre-cooling treatment process can be effectively reduced, the cyclic utilization of the ice crystal wastewater can be realized, and the discharge of the wastewater is reduced.
In this embodiment, utilize water that the ice crystal melts to form and supernatant to carry out the heat transfer to precooling the supernatant, thereby realize energy-conservation. Specifically, a heat exchanger can be arranged in the pre-cooling tank, water formed by melting ice crystals is conveyed into the heat exchanger, and the heat exchanger is utilized to exchange heat between the water formed by melting ice crystals and the supernatant so as to absorb heat of the supernatant, thereby pre-cooling the supernatant.
Optionally, the separated ice crystals may be stored in an ice crystal storage tank, a conveying device is arranged between the ice crystal storage tank and the heat exchanger, and the conveying device may convey water formed by melting the ice crystals in the ice crystal storage tank to the heat exchanger to pre-cool the supernatant. The water after heat exchange can be conveyed back to the ice crystal storage tank through the conveying device to exchange heat with the ice crystals in the ice crystal storage tank, so that the melting of the ice crystals is realized. In this embodiment, the conveying device may be a water pump, so that the water formed by melting the ice crystals is pumped to the heat exchanger.
In some embodiments, the cooling temperature for pre-cooling the supernatant may be 0 ℃ to 5 ℃, and may also be 5 ℃ to 10 ℃. When the difference between the cooling temperature of the pre-cooling treatment of the supernatant and the temperature of the freezing and concentrating treatment is larger, the system consumes more energy, the freezing and concentrating treatment time is longer, and the purity of the ice crystals in the freezing and concentrating treatment process is not high. Therefore, the cooling temperature for the pre-cooling treatment of the supernatant is preferably 0 to 5 ℃ from the viewpoints of economic cost, time, and effect of concentrating the radioactive waste liquid. The time for the pre-cooling treatment depends on the volume of the supernatant and the temperature of the pre-cooling treatment, and it should be noted that the temperature of the pre-cooling treatment in this embodiment is only given for illustration.
In operation S104, after the volume of the formed ice crystals accounts for 30% to 90% of the volume of the pre-cooled supernatant, the ice crystals may be separated and the radioactive waste liquid may be concentrated, wherein the volume of the formed ice crystals may be 30%, 50%, 60%, 70%, 80%, 90%, and the like, of the volume of the pre-cooled supernatant. In the volume ratio range, the obtained ice crystals are pure, the radioactive substances are less, and the concentration of the obtained concentrated radioactive waste liquid can reach 5-10 times of that of radioactive waste water which is not subjected to freeze concentration treatment, so that the volume of the waste liquid is greatly reduced. In some embodiments, if multiple concentration is used, the concentration of the concentrated radioactive waste liquid can be further increased, for example, the concentration of the concentrated radioactive waste liquid can be about 15-20 times of the concentration of the radioactive waste liquid without freeze concentration, thereby indicating that the radioactive waste liquid can be effectively enriched by means of pre-cooling treatment and freeze concentration.
Further, the ice crystals can be separated and the radioactive waste liquid can be concentrated after the supernatant is frozen at a predetermined temperature for a predetermined time, so that the volume of the formed ice crystals reaches 30% -90% of the volume of the supernatant, the volume of the waste liquid is greatly reduced, and the concentration of the radioactive waste liquid is realized. In some embodiments, the pre-set temperature for freeze concentration of the pre-cooled supernatant in operation S103 may be-5 ℃ to-25 ℃, for example, -25 ℃, to-10 ℃, to-5 ℃, and the like. It can also be operated at higher altitude and in extreme winter, such as-30 deg.C, -40 deg.C, etc.
Further, the preset time for performing the freeze concentration treatment on the pre-cooled supernatant may be 4h to 70h, for example, 4h, 10h, 15h, 30h, 50h, 70h, and the like. The time for freeze concentration can be determined by the volume of the supernatant, the temperature of the natural environment, and the magnitude of the temperature difference between the pre-cooling treatment and the freeze concentration, and is not limited to the time for freeze concentration as exemplified in the present embodiment.
In the embodiment of the invention, the pre-cooled supernatant is directly subjected to heat exchange with cold energy in a natural environment, so that the solvent in the pre-cooled supernatant is frozen to form ice crystals to be separated out, and the enrichment of radioactive substances is realized. Compared with evaporation concentration, the energy consumption of freeze concentration is less, the damage to equipment is less, additional heat exchange equipment is not needed, and the cost and the use are reduced. And the water of the melted ice crystals can be recycled, thereby reducing the discharge of waste water. In addition, the treatment of radioactive waste liquid is an uninterrupted process, and a low-carbon and environment-friendly mode is needed for treatment in long-term development.
In some embodiments, the pre-cooled supernatant may be transferred to a freeze concentration tank to freeze concentrate the supernatant. When the ice crystals formed by freezing and the concentrated radioactive waste liquid are separated, the concentrated radioactive waste liquid in the freezing concentration tank can be discharged, and then the ice crystals are transferred out from the freezing concentration tank, so that the radioactive waste liquid contaminated on the surfaces of the ice crystals is reduced.
Particularly, a liquid outlet can be arranged at the bottom of the freezing concentration tank, an outlet is arranged at the top of the freezing concentration tank, and a filter screen capable of moving up and down is arranged in the freezing concentration tank. During separation, the liquid outlet at the bottom of the freeze concentration tank is firstly opened, concentrated radioactive waste liquid is discharged, and then the filter screen is controlled to move upwards from the bottom to the top of the freeze concentration tank so as to transfer ice crystals in the freeze concentration tank out of the outlet.
In some embodiments, before the ice crystals are transferred, the surfaces of the ice crystals can be washed, so that the residue of concentrated radioactive waste liquid on the surfaces of the ice crystals can be effectively reduced, and the concentration of radioactive substances in water after the ice crystals are melted can be reduced.
The embodiment of the application also provides a system for treating the radioactive liquid waste, and the system adopts the method for treating the radioactive liquid waste in the embodiment to realize the treatment of the radioactive liquid waste. Wherein, this system includes: a stock solution tank, a flocculation precipitation tank, a pre-cooling tank and a freezing concentration tank.
Wherein, the stock solution jar is used for storing radioactive liquid waste. And the flocculation precipitation tank is connected with the raw liquid tank and is used for receiving the radioactive waste liquid and carrying out flocculation precipitation treatment on the radioactive waste liquid so as to obtain a supernatant after precipitation. The pre-cooling tank is connected with the flocculation precipitation tank and is used for receiving the supernatant and pre-cooling the supernatant. The freezing concentration tank is connected with the precooling tank and used for receiving the precooled supernatant and carrying out freezing concentration treatment on the precooled supernatant so as to freeze at least part of water in the supernatant to form ice crystals and concentrate the residual liquid to form concentrated radioactive waste liquid. Wherein, the cold energy of the freeze concentration treatment comes from the natural cold energy in the environment.
Fig. 2 is a schematic diagram of a configuration of a system for treating radioactive waste according to one embodiment of the present application. The system for treating radioactive waste will be described in detail below with reference to fig. 2. As shown in fig. 2, the system for treating radioactive waste liquid includes a stock solution tank 1, a flocculation and precipitation tank 2, a pre-cooling tank 3, and a freeze concentration tank 4.
In some embodiments, the feed tank 1 is used for holding radioactive waste. The top of the raw liquid tank 1 is provided with a water outlet, the top of the flocculation and precipitation tank 2 is provided with a water inlet, the water inlet is communicated with the water outlet of the raw liquid tank 1 so as to transfer the radioactive waste liquid in the raw liquid tank 1 to the flocculation and precipitation tank 2, and the flocculation and precipitation tank 2 can receive the radioactive waste liquid to perform flocculation and precipitation treatment on the radioactive waste liquid, so that impurities in the radioactive waste liquid are removed.
Specifically, a radioactive waste liquid conveying device, such as a pump, is arranged between the water outlet of the raw liquid tank 1 and the water inlet of the flocculation and sedimentation tank 2, and can suck the radioactive waste liquid in the raw liquid tank 1 into the flocculation and sedimentation tank 2. After the radioactive waste liquid is transferred to the flocculation and precipitation tank 2, a flocculating agent may be added to the flocculation and precipitation tank 2 to flocculate and precipitate impurities in the radioactive waste liquid. After the flocculation precipitation treatment, the radioactive waste liquid can be layered to obtain supernatant and lower-layer impurity precipitate.
Further, the supernatant may be subjected to a pre-cooling treatment using a pre-cooling tank 3. The supernatant formed after the flocculation may be transferred to the pre-cooling tank 3 for pre-cooling in the pre-cooling tank 3. In some embodiments, the top of the flocculation and sedimentation tank 2 is provided with a water outlet, the top of the pre-cooling tank 3 is provided with a water inlet, the water inlet is connected with the water outlet on the top of the flocculation and sedimentation tank 2 so as to transfer the radioactive waste liquid in the flocculation and sedimentation tank 2 into the pre-cooling tank 3, and the pre-cooling tank 3 can receive the supernatant to perform pre-cooling treatment on the supernatant. Specifically, a supernatant conveying device is arranged between the water outlet of the flocculation precipitation tank 2 and the water inlet of the pre-cooling tank 3, and supernatant in the flocculation precipitation tank 2 can be sucked into the pre-cooling tank 3. Wherein, the supernatant fluid conveying device can be a pump.
In this embodiment, the pre-cooled supernatant may be transferred to the freeze concentration tank 4 to perform freeze concentration processing on the supernatant. Specifically, the top of the freezing concentration tank 4 can be provided with a water inlet, the top of the pre-cooling tank 3 can be provided with a water outlet, the water inlet of the freezing concentration tank 4 is connected with the water outlet of the pre-cooling tank 3, so that the supernatant in the pre-cooling tank 3 is transferred into the freezing concentration tank 4, the freezing concentration tank 4 can receive the pre-cooled supernatant and carry out freezing concentration treatment on the pre-cooled supernatant, so that at least part of water in the supernatant is frozen to form ice crystals, and the residual liquid is concentrated to form concentrated radioactive waste liquid. The cold energy used by the freeze concentration tank 4 is natural cold energy in the environment.
In some embodiments, a supernatant conveying device is arranged between the water inlet of the freeze concentration tank 4 and the water outlet of the pre-cooling tank 3, and the supernatant conveying device can be used for sucking the supernatant in the pre-cooling tank 3 into the freeze concentration tank 4. Illustratively, the supernatant delivery device may be a pump.
In some embodiments, the bottom of the freeze concentration tank 4 is provided with a liquid outlet for discharging the concentrated radioactive waste liquid in the freeze concentration tank 4 to achieve separation between the ice crystals and the concentrated radioactive waste liquid.
As shown in fig. 2, in some embodiments, the system for treating radioactive waste further comprises a concentrate reservoir 6. The top of concentrate storage tank 6 is equipped with the inlet, and this inlet is connected with the liquid outlet of freezing concentrated jar 4 bottoms to in concentrated radioactive waste liquid in freezing concentrated jar 4 shifts to concentrate storage tank 6, concentrate storage tank 6 can receive and store concentrated radioactive waste liquid.
In some embodiments, the top of the freeze concentration tank 4 is provided with an outlet, and a filter screen 7 is further provided in the freeze concentration tank 4, wherein the filter screen 7 is arranged to move up and down in the freeze concentration tank 4, so as to remove ice crystals from the outlet at the top of the freeze concentration tank 4. Specifically, the initial position of the filter screen 7 is located at the bottom of the freeze concentration tank 4 before freeze concentration starts.
In the freeze concentration process, the freeze concentration tank 4 may be placed in a low temperature environment to freeze concentrate the supernatant in the freeze concentration tank 4. Wherein, part of water in the freezing concentration tank 4 is frozen to form ice crystals which are positioned above the filter screen 7. When the filter screen 7 is moved upwards, the ice crystals can be driven to move upwards, and then the ice crystals are removed from the outlet at the top of the freezing and concentrating tank 4. And the concentrated radioactive waste liquid can flow to the bottom of the freezing concentration tank 4 from the filter screen 7, so that the separation of the ice crystals and the concentrated radioactive waste liquid is realized.
In some embodiments, when it is desired to separate the ice crystals and concentrate the radioactive waste, the concentrated radioactive waste can be discharged from the outlet at the bottom of the freeze concentration tank 4, and the filter screen 7 is controlled to move upward to remove the ice crystals from the outlet at the top of the freeze concentration tank 4.
In addition, before the ice crystals are transferred, the surfaces of the ice crystals can be washed by water, so that radioactive waste liquid polluted on the surfaces of the ice crystals is removed, and then the washed ice crystals are transferred out of the freeze concentration tank 4. Before washing, the filter screen 7 can be moved upwards for a certain distance, so that a space is reserved between the ice crystals and the bottom of the freeze concentration tank 4, water after washing can flow down from the ice crystals and the filter screen 7, and water containing radioactive substances after washing is prevented from remaining on the ice crystals. In this embodiment, the rinsed water may be retained in the freeze concentration tank 4 to be subjected to freeze concentration treatment together with the subsequent radioactive liquid waste.
As shown in fig. 2, in some embodiments, the system for treating radioactive waste further comprises an ice crystal storage tank 5, the ice crystal storage tank 5 being connected to the freeze concentration tank 4 for storing separated ice crystals. Specifically, the ice crystal storage tank 5 is provided at the top thereof with an inlet connected to an outlet provided at the top of the freeze concentration tank 4, so that the ice crystals in the freeze concentration tank 4 can be transferred to the ice crystal storage tank 5. Optionally, a conveying device (e.g., a conveyor belt) is connected between the outlet of the freeze concentration tank 4 and the inlet of the ice crystal storage tank 5, and the conveying device can convey the ice crystals to the ice crystal storage tank 5. In addition, the ice crystals in this embodiment are in a block shape, and the ice crystals can be transferred from the freeze concentration tank 4 to the ice crystal storage tank 5 by using a lifting tool.
As shown in fig. 2, a heat exchanger 8 may be provided in the pre-cooling tank 3, and a conveying device 9 is connected between the heat exchanger 8 and the ice crystal storage tank 5. The conveying device 9 is used for conveying water formed by melting ice crystals in the ice crystal storage tank 5 into the heat exchanger 8, the heat exchanger 8 is used for exchanging heat between the water formed by melting the ice crystals and supernatant in the precooling tank 3 so as to absorb heat of the supernatant, the water after heat exchange can be conveyed back into the ice crystal storage tank 5 through the conveying device 9 to exchange heat with the ice crystals removed from the freezing concentration tank 4 so as to melt the ice crystals into water, and the water is circulated repeatedly.
In some embodiments, a delivery device 9 may be provided in the ice crystal storage tank 5 to efficiently deliver water formed by melting ice crystals in the ice crystal storage tank 5 to the heat exchanger 8. The delivery device 9 may be a suction pump. In addition, the heat exchanger 8 can be a coiled pipe, so that the heat exchange area is increased, and the precooling efficiency is improved.
In this embodiment, the stock solution tank 1, the flocculation and precipitation tank 2, the pre-cooling tank 3, the freezing and concentration tank 4, the ice crystal storage tank 5 and the concentrated solution storage tank 6 in the radioactive waste liquid treatment system are all provided with shielding layers to prevent the radioactive waste liquid from radiating other equipment and the environment. The shielding material lead can be selected as the shielding material of the tank body, namely, the tank body is the shielding layer. Other materials with better heat transfer performance can be selected as the tank body, and a shielding layer is arranged on the tank body, for example, a radiation-proof material layer can be coated on the surface of a stainless steel tank body, so that the damage of radioactive waste liquid to people or the environment is reduced. And shielding devices, such as a box body for placing radiation protection, can be arranged on the outer covers of the stock solution tank 1, the flocculation precipitation tank 2, the pre-cooling tank 3, the freezing concentration tank 4, the ice crystal storage tank 5 and the concentrated solution storage tank 6. In addition, the communicating mode between the jar body in this application can be for the union coupling, and the pipe that uses also possesses the function of protecting against radiation.
The system for treating the radioactive liquid waste in the embodiment of the application is characterized in that:
and pumping the radioactive waste liquid stored in the raw liquid tank 1 into a flocculation precipitation tank 2 through a pump for flocculation precipitation to obtain supernatant after precipitation. And then, pumping the supernatant in the flocculation precipitation tank 2 into a pre-cooling tank 3, and pre-cooling the supernatant to obtain pre-cooled supernatant, wherein the temperature of the pre-cooling treatment is 0-5 ℃. Then, the pre-cooled supernatant is pumped into a freezing concentration tank 4 for freezing concentration treatment, so that at least part of water in the supernatant is frozen to form ice crystals, and the residual liquid is concentrated to form concentrated radioactive waste liquid. Wherein, the cold energy of the freeze concentration treatment comes from the natural cold energy in the environment.
When the volume of the formed ice crystals accounts for 30-90% of the volume of the precooled supernatant, the ice crystals can be separated and the radioactive waste liquid can be concentrated. The bottom of the freeze concentration tank 4 is provided with a liquid outlet, and concentrated radioactive waste liquid in the freeze concentration tank 4 can be discharged through the liquid outlet. The top of concentrate storage tank 6 is equipped with the inlet, and this inlet is connected with the liquid outlet of freezing concentrated jar 4 bottoms, and concentrate storage tank 6 is used for receiving and stores concentrated radioactive waste liquid, realizes the enrichment of radioactive substance.
The top of the freeze concentration tank 4 is provided with an outlet, a filter screen 7 is arranged in the freeze concentration tank 4, the filter screen 7 is arranged to move up and down in the freeze concentration tank 4, and after the concentrated radioactive waste liquid is discharged, the ice crystals are moved out from the outlet of the freeze concentration tank 4 through the upward movement of the filter screen 7 and transferred to the ice crystal storage tank 5 to be stored and separated to obtain the ice crystals.
Water formed by melting of ice crystals in the ice crystal storage tank 5 is conveyed into the heat exchanger 8 through the conveying device 9, the heat exchanger 8 exchanges heat between the water formed by melting of the ice crystals and the supernatant, and precooling treatment of the supernatant is achieved. The water after heat exchange is conveyed back to the ice crystal storage tank 5 through the conveying device 9, and then the ice crystals in the ice crystal storage tank 5 are melted to form water, so that the water is circulated repeatedly. In the treatment process, all the operation processes are subjected to radiation protection treatment, so that the harm of radioactive substances to people or environment is avoided.
In some embodiments, to achieve a further level of radioactive waste treatment, multiple radioactive waste treatment systems can be connected in series to further increase the concentration of the radioactive waste.
The technical solution of the present application is clearly and completely described below with reference to specific embodiments. It should be apparent that the described embodiment is one embodiment of the present application and not all embodiments.
Example 1
The method comprises the following steps of firstly, pumping the radioactive waste water in a raw liquid tank into a flocculation precipitation tank, carrying out flocculation precipitation by using a polyaluminium chloride flocculant, preliminarily removing partial impurities in the radioactive waste liquid, and obtaining supernatant after precipitation.
And secondly, pumping the supernatant in the flocculation precipitation tank into a pre-cooling tank, and pre-cooling the supernatant to 1 ℃.
And thirdly, pumping the pre-cooled supernatant into a freezing concentration tank for freezing concentration, so that at least part of water in the supernatant is frozen to form ice crystals, and the residual liquid is concentrated to form concentrated radioactive waste liquid, wherein the cold energy of freezing concentration treatment is natural cold energy in the environment, the freezing concentration temperature is-13 ℃, and the freezing concentration time is 6 hours.
And fourthly, separating the ice crystals formed by freezing concentration from the concentrated radioactive waste liquid, and transferring the ice crystals to an ice crystal storage tank for storage. And transferring the concentrated radioactive waste liquid to a concentrated liquid tank for storage, increasing the concentration of radioactive substances in the concentrated radioactive waste liquid, and transferring to the next process for subsequent treatment.
The water formed by melting the ice crystals in the ice crystal storage tank is conveyed into a heat exchanger of a pre-cooling tank by a conveying device (a water suction pump), pre-cooling treatment is carried out on supernatant by the heat exchanger, and the water formed by melting the ice crystals after heat exchange is pumped back into the ice crystal storage tank by the water suction pump to melt the ice crystals.
Example 2
The process for treating radioactive wastewater by freeze concentration comprises 4 steps:
firstly, pumping the radioactive waste water in the raw liquid tank into a flocculation precipitation tank, adding a chemical reagent ammonium phosphate as a flocculating agent for flocculation precipitation, and preliminarily removing partial impurities in the radioactive waste liquid.
And secondly, pumping the supernatant in the flocculation precipitation tank into a pre-cooling tank, and pre-cooling the supernatant to 5 ℃.
And thirdly, pumping the pre-cooled supernatant into a freezing concentration tank for freezing concentration to freeze at least part of water in the supernatant to form ice crystals, and concentrating the residual liquid to form concentrated radioactive waste liquid. Wherein the cold energy of the freeze concentration treatment is natural cold energy in the environment, the freeze concentration temperature is-18 ℃, and the freeze concentration time is 4h.
And fourthly, separating the ice crystals formed by freezing concentration from the concentrated radioactive waste liquid, and transferring the ice crystals to an ice crystal storage tank for storage through an outlet formed in the top of the freezing concentration tank. Transferring the concentrated radioactive waste liquid to a concentrated liquid tank for storage through a water outlet formed in the bottom of the freeze concentration tank, increasing the concentration of radioactive substances in the concentrated radioactive waste liquid, and transferring the concentrated radioactive waste liquid to the next process for subsequent treatment.
The water formed by melting the ice crystals in the ice crystal storage tank after heat exchange is conveyed to a heat exchanger in a precooling tank through a conveying device (a water suction pump), precooling treatment is carried out on supernatant by adopting the heat exchanger, and the water formed by melting the ice crystals after heat exchange is pumped back to the ice crystal storage tank through the water suction pump to melt the ice crystals.
Example 3
The process for treating radioactive wastewater by freeze concentration comprises 4 steps:
firstly, pumping the radioactive waste water in the raw liquid tank into a flocculation precipitation tank, adding a chemical reagent ammonium phosphate as a flocculating agent for flocculation precipitation, and preliminarily removing partial impurities in the radioactive waste liquid.
And secondly, pumping the supernatant in the flocculation precipitation tank into a pre-cooling tank, pre-cooling the supernatant to 5 ℃ and obtaining the pre-cooled supernatant.
And thirdly, pumping the pre-cooled supernatant into a freezing and concentrating tank for freezing and concentrating, so that at least part of water in the supernatant is frozen to form ice crystals, and the residual liquid is concentrated to form concentrated radioactive waste liquid. Wherein the cold energy of the freeze concentration treatment is natural cold energy in the environment, the freeze concentration temperature is-10 ℃, the freeze concentration time is 20h, and the formed ice crystals account for 90% of the volume of the pre-cooled supernatant.
And fourthly, separating the ice crystals formed by freezing concentration and the concentrated radioactive waste liquid, and transferring the ice crystals into an ice crystal storage tank for storage through an outlet formed in the top of the freezing concentration tank. The water formed by melting the ice crystals after heat exchange is conveyed to a heat exchanger in a precooling tank by a conveying device (a water pump), the supernatant is precooled by the heat exchanger, and the water formed by melting the ice crystals after heat exchange is pumped back to the ice crystal storage tank by the water pump to melt the ice crystals. In addition, the concentrated radioactive waste liquid is transferred to a concentrated liquid tank for storage through a water outlet formed in the bottom of the freezing concentration tank, the concentration of radioactive substances in the concentrated radioactive waste liquid is increased, and the concentrated radioactive waste liquid is transferred to the next process for subsequent treatment.
Example 4
The process for treating radioactive wastewater by freeze concentration comprises 4 steps:
firstly, pumping the radioactive waste water in the raw liquid tank into a flocculation precipitation tank, adding a chemical reagent ammonium phosphate as a flocculating agent for flocculation precipitation, and preliminarily removing partial impurities in the radioactive waste liquid.
And secondly, pumping the supernatant in the flocculation precipitation tank into a pre-cooling tank, pre-cooling the supernatant to 0-5 ℃ and obtaining the pre-cooled supernatant.
And thirdly, pumping the pre-cooled supernatant into a freezing concentration tank for freezing concentration, so that at least part of water in the supernatant is frozen to form ice crystals, and the residual liquid is concentrated to form concentrated radioactive waste liquid, wherein the cold energy of freezing concentration treatment is natural cold energy in the environment, the freezing concentration temperature is-18 to-13 ℃, and the freezing concentration time is 4 to 30 hours.
Fourthly, when the volume of the formed ice crystals accounts for 60% of the volume of the precooled supernatant, separating the ice crystals formed by freezing and concentration and concentrating the radioactive waste liquid. The ice crystals are moved to the mouth of the freeze concentration tank through the filter screen, and the ice crystals are transferred to an adjacent ice crystal storage tank for storage through an outlet formed in the top of the freeze concentration tank. The ice crystals may also be surface washed prior to their transfer to remove surface-contaminated concentrated radioactive liquid, the liquid from which the ice crystals are washed remaining in the freeze concentration tank. Transferring the concentrated radioactive waste liquid to a concentrated liquid tank for storage through a water outlet formed in the bottom of the freeze concentration tank, increasing the concentration of radioactive substances in the concentrated radioactive waste liquid, and transferring the concentrated radioactive waste liquid to the next process for subsequent treatment.
In addition, water is formed by melting ice crystals in the ice crystal storage tank after heat exchange, the water formed by melting the ice crystals is conveyed to a heat exchanger in a precooling tank through a conveying device (a water suction pump), precooling treatment is carried out on supernate by adopting the heat exchanger, and the water formed by melting the ice crystals after heat exchange is pumped back to the ice crystal storage tank through the water suction pump so as to melt the ice crystals.
The present invention has been described in detail with reference to the drawings and examples, but the present invention is not limited to the examples, and various changes can be made within the knowledge of those skilled in the art without departing from the spirit of the present invention. The prior art can be adopted in the content which is not described in detail in the invention.
Claims (17)
1. A method of treating radioactive waste, comprising:
performing flocculation precipitation treatment on the radioactive waste liquid to obtain supernatant after precipitation;
pre-cooling the supernatant;
freezing and concentrating the pre-cooled supernatant to freeze at least part of water in the supernatant to form ice crystals, and concentrating the residual liquid to form concentrated radioactive waste liquid; wherein the cold energy of the freeze concentration treatment is from natural cold energy in the environment;
separating the ice crystals and concentrating the radioactive waste liquid.
2. The method according to claim 1, wherein the flocculating and settling treatment comprises: adding one or more flocculants to the radioactive spent liquor;
the flocculant comprises: at least one of aluminum salt, iron salt, phosphate and manganese salt.
3. The method of claim 1, wherein the supernatant is pre-cooled using natural cold energy.
4. The method of claim 3, wherein after the ice crystals are formed, the pre-cooling of the supernatant is performed using water from the melting of the ice crystals.
5. The method of claim 4,
transferring the supernatant into a pre-cooling tank, wherein a heat exchanger is arranged in the pre-cooling tank;
and conveying the water formed by melting the ice crystals into the heat exchanger, and exchanging heat between the water formed by melting the ice crystals and the supernatant by using the heat exchanger so as to pre-cool the supernatant.
6. The method of claim 1, wherein the ice crystals are separated and the radioactive waste concentrated after the ice crystals are formed in a volume of 30% to 90% of the volume of the pre-cooled supernatant.
7. The method of claim 6, wherein the ice crystals are separated and the radioactive waste liquid is concentrated after the supernatant is frozen at a predetermined temperature for a predetermined time.
8. The method of claim 7,
transferring the pre-cooled supernatant into a freezing concentration tank to freeze and concentrate the supernatant;
the separating the ice crystals and concentrating the radioactive spent liquor comprises: and discharging the concentrated radioactive waste liquid in the freezing concentration tank, and transferring the ice crystals out of the freezing concentration tank.
9. The method according to claim 8, wherein the freeze concentration tank is provided with a liquid outlet at the bottom and an outlet at the top, and a filter screen is arranged in the freeze concentration tank and can move up and down in the freeze concentration tank;
the separating the ice crystals and the concentrated radioactive spent solution in the freeze concentration tank, comprising:
opening the liquid outlet, and discharging the concentrated radioactive waste liquid in the freezing concentration tank;
controlling the filter screen to move upwards from the bottom to the top of the freeze concentration tank so as to transfer the ice crystals in the freeze concentration tank out of the outlet.
10. The method of claim 8, further comprising:
rinsing the surface of the ice crystals prior to transferring the ice crystals.
11. A system for treating radioactive liquid waste, wherein the system employs the method according to any one of claims 1 to 10 to achieve the treatment of the radioactive liquid waste, the system comprising:
a raw liquid tank for storing the radioactive waste liquid;
the flocculation precipitation tank is connected with the raw liquid tank and is used for receiving the radioactive waste liquid and carrying out flocculation precipitation treatment on the radioactive waste liquid so as to obtain supernatant after precipitation;
the pre-cooling tank is connected with the flocculation precipitation tank and is used for receiving the supernatant and pre-cooling the supernatant;
a freezing concentration tank connected with the pre-cooling tank and used for receiving the pre-cooled supernatant and carrying out freezing concentration treatment on the pre-cooled supernatant so as to freeze at least part of water in the supernatant to form ice crystals and concentrate the residual liquid to form concentrated radioactive waste liquid;
wherein the cold energy used by the freezing concentration tank comes from natural cold energy in the environment.
12. The system of claim 11, wherein the bottom of the freeze concentration tank is provided with a liquid outlet for discharging concentrated radioactive liquid waste from the freeze concentration tank.
13. The system of claim 12, further comprising:
the concentrated solution storage tank, the top of concentrated solution storage tank is equipped with the inlet, the inlet with the liquid outlet of freezing concentrated tank bottoms portion is connected, the concentrated solution storage tank is used for receiving and storing concentrated radioactive waste liquid.
14. The system of claim 12,
the top of the freezing concentration tank is provided with an outlet;
a filter screen is arranged in the freeze concentration tank, and the filter screen can move up and down in the freeze concentration tank and is used for removing the ice crystals from the outlet.
15. The system of claim 11, further comprising:
and the ice crystal storage tank is connected with the freezing concentration tank and is used for storing the ice crystals obtained by separation.
16. The system of claim 15,
a heat exchanger is arranged in the pre-cooling tank, and a conveying device is connected between the heat exchanger and the ice crystal storage tank; wherein the content of the first and second substances,
the conveying device is used for conveying the water formed by melting the ice crystals in the ice crystal storage tank into the heat exchanger, and the heat exchanger is used for exchanging heat between the water formed by melting the ice crystals and the supernatant.
17. The system according to any one of claims 11-16, wherein the stock tank, the flocculation and precipitation tank, the pre-cooling tank and the freeze concentration tank are provided with shielding layers.
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Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5055237A (en) * | 1990-08-14 | 1991-10-08 | Technology International Incorporated | Method of compacting low-level radioactive waste utilizing freezing and electrodialyzing concentration processes |
| KR20010016875A (en) * | 1999-08-05 | 2001-03-05 | 송영채 | Method and Apparatus of Freeze Concentration for Wastewater Treatment |
| CN105448373A (en) * | 2015-11-06 | 2016-03-30 | 西南科技大学 | Quick uranium removal and salt reduction method for high-salt uranium-containing waste water or waste liquid |
| CN112489846A (en) * | 2020-11-26 | 2021-03-12 | 中国核动力研究设计院 | System and method for treating radioactive waste liquid containing chlorine ions |
| CN112715715A (en) * | 2020-12-24 | 2021-04-30 | 昆明弘承食品科技有限公司 | Coffee feed liquid freezing and concentrating method and device |
| CN113387498A (en) * | 2021-06-22 | 2021-09-14 | 光大环保技术装备（常州）有限公司 | Disposal system and disposal method for freezing and concentrating landfill leachate concentrated water |
| CN215161844U (en) * | 2021-04-14 | 2021-12-14 | 西北工业大学 | Device for reducing concentration of heavy metal in water body through freeze concentration |
-
2022
- 2022-12-02 CN CN202211537898.7A patent/CN115831424B/en active Active
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5055237A (en) * | 1990-08-14 | 1991-10-08 | Technology International Incorporated | Method of compacting low-level radioactive waste utilizing freezing and electrodialyzing concentration processes |
| KR20010016875A (en) * | 1999-08-05 | 2001-03-05 | 송영채 | Method and Apparatus of Freeze Concentration for Wastewater Treatment |
| CN105448373A (en) * | 2015-11-06 | 2016-03-30 | 西南科技大学 | Quick uranium removal and salt reduction method for high-salt uranium-containing waste water or waste liquid |
| CN112489846A (en) * | 2020-11-26 | 2021-03-12 | 中国核动力研究设计院 | System and method for treating radioactive waste liquid containing chlorine ions |
| CN112715715A (en) * | 2020-12-24 | 2021-04-30 | 昆明弘承食品科技有限公司 | Coffee feed liquid freezing and concentrating method and device |
| CN215161844U (en) * | 2021-04-14 | 2021-12-14 | 西北工业大学 | Device for reducing concentration of heavy metal in water body through freeze concentration |
| CN113387498A (en) * | 2021-06-22 | 2021-09-14 | 光大环保技术装备（常州）有限公司 | Disposal system and disposal method for freezing and concentrating landfill leachate concentrated water |
Non-Patent Citations (1)
| Title |
|---|
| 黄昌海, 许道铭, 刘尚勇, 周丽华, 张依群, 杨宏, 赵有君: "碱性铀沉淀母液治理新工艺", 铀矿冶, vol. 20, no. 1, pages 35 - 41 * |
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