CN115831424B - Method and system for treating radioactive waste liquid - Google Patents
Method and system for treating radioactive waste liquid Download PDFInfo
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- CN115831424B CN115831424B CN202211537898.7A CN202211537898A CN115831424B CN 115831424 B CN115831424 B CN 115831424B CN 202211537898 A CN202211537898 A CN 202211537898A CN 115831424 B CN115831424 B CN 115831424B
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- 239000007788 liquid Substances 0.000 title claims abstract description 180
- 239000002901 radioactive waste Substances 0.000 title claims abstract description 157
- 238000000034 method Methods 0.000 title claims abstract description 48
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 227
- 239000013078 crystal Substances 0.000 claims abstract description 168
- 239000006228 supernatant Substances 0.000 claims abstract description 139
- 238000001816 cooling Methods 0.000 claims abstract description 80
- 238000007710 freezing Methods 0.000 claims abstract description 78
- 230000008014 freezing Effects 0.000 claims abstract description 77
- 238000001556 precipitation Methods 0.000 claims abstract description 71
- 230000003311 flocculating effect Effects 0.000 claims abstract description 3
- 230000001376 precipitating effect Effects 0.000 claims abstract description 3
- 238000005189 flocculation Methods 0.000 claims description 59
- 230000016615 flocculation Effects 0.000 claims description 58
- 230000008018 melting Effects 0.000 claims description 25
- 238000002844 melting Methods 0.000 claims description 25
- 239000012141 concentrate Substances 0.000 claims description 13
- 239000000243 solution Substances 0.000 claims description 7
- 239000011550 stock solution 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
- 150000002696 manganese Chemical class 0.000 claims description 4
- AZDRQVAHHNSJOQ-UHFFFAOYSA-N alumane Chemical class [AlH3] AZDRQVAHHNSJOQ-UHFFFAOYSA-N 0.000 claims description 3
- 238000007599 discharging Methods 0.000 claims description 3
- 239000008394 flocculating agent Substances 0.000 claims description 2
- 150000003839 salts Chemical class 0.000 claims description 2
- 238000005086 pumping Methods 0.000 description 18
- 239000002354 radioactive wastewater Substances 0.000 description 16
- 239000012535 impurity Substances 0.000 description 15
- 239000000941 radioactive substance Substances 0.000 description 13
- 238000005265 energy consumption Methods 0.000 description 11
- 238000001704 evaporation Methods 0.000 description 6
- 239000012530 fluid Substances 0.000 description 6
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- 230000000694 effects Effects 0.000 description 5
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- 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
- 238000011010 flushing procedure Methods 0.000 description 4
- 239000003153 chemical reaction reagent Substances 0.000 description 3
- 238000005516 engineering process Methods 0.000 description 3
- 239000000463 material Substances 0.000 description 3
- 239000002244 precipitate Substances 0.000 description 3
- 230000005855 radiation Effects 0.000 description 3
- 238000000926 separation method 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
- XLYOFNOQVPJJNP-UHFFFAOYSA-M hydroxide Chemical compound [OH-] XLYOFNOQVPJJNP-UHFFFAOYSA-M 0.000 description 2
- 230000007774 longterm Effects 0.000 description 2
- 230000002285 radioactive effect Effects 0.000 description 2
- 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
- 230000015572 biosynthetic process Effects 0.000 description 1
- 229910052799 carbon Inorganic materials 0.000 description 1
- 239000000356 contaminant Substances 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000008878 coupling Effects 0.000 description 1
- 238000010168 coupling process Methods 0.000 description 1
- 238000005859 coupling reaction Methods 0.000 description 1
- 238000005202 decontamination Methods 0.000 description 1
- 230000003588 decontaminative effect Effects 0.000 description 1
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- 150000002505 iron Chemical class 0.000 description 1
- 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
- 235000015073 liquid stocks Nutrition 0.000 description 1
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- 235000002867 manganese chloride Nutrition 0.000 description 1
- 239000011565 manganese chloride Substances 0.000 description 1
- 229940099607 manganese chloride Drugs 0.000 description 1
- 229940099596 manganese sulfate Drugs 0.000 description 1
- 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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- 229920002401 polyacrylamide Polymers 0.000 description 1
- 238000003672 processing method Methods 0.000 description 1
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- 239000002904 solvent Substances 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: flocculating and precipitating the radioactive waste liquid to obtain a 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 rest liquid to form concentrated radioactive waste liquid, wherein the cold energy of the freezing and concentrating treatment is natural cold energy in the environment; separating ice crystals and concentrating radioactive waste liquid. The embodiment of the application also provides a system for treating radioactive waste liquid.
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 nuclides, which is generated in the processes of nuclear facility operation, retirement, factory site decontamination and the like. With the great development of nuclear power technology, radioactive waste liquid stock is increasingly increased, and treatment is needed. Although the existing treatment technologies are mature and can effectively treat radioactive waste liquid, the treatment technologies can have the problems of high operation cost, high energy consumption, easy corrosion of equipment and the like. For example, the most widely used treatment method is flocculation precipitation-evaporation concentration-ion exchange coupling, wherein the main function is evaporation concentration, but the treatment method consumes a large amount of energy during long-term operation and affects the service life of equipment during evaporation.
Disclosure of Invention
The present application has been made in view of the above problems, and it is an object of the present application to provide a method and a system for treating radioactive waste that overcomes or at least partially solves the above problems.
According to a first aspect of an embodiment of the present application, there is provided a method of treating radioactive waste, comprising: flocculating and precipitating the radioactive waste liquid to obtain a 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 rest liquid to form concentrated radioactive waste liquid, wherein the cold energy of the freezing and concentrating treatment is natural cold energy in the environment; separating ice crystals and concentrating radioactive waste liquid.
According to a second aspect of embodiments of the present application, a system for treating radioactive waste is provided. The system adopts the method for treating radioactive waste liquid in the embodiment to realize the treatment of radioactive waste liquid, and comprises the following steps: 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 a supernatant after precipitation; a pre-cooling tank connected with the flocculation precipitation tank for receiving supernatant and pre-cooling the supernatant; the freezing and concentrating tank is connected with the pre-cooling tank and is used for receiving the pre-cooled supernatant and carrying out freezing and concentrating treatment on the supernatant so that at least part of water in the supernatant is frozen to form ice crystals, and the rest liquid is concentrated to form concentrated radioactive waste liquid; wherein, the cold energy used by the freezing and concentrating tank comes from natural cold energy in the environment.
According to the method for treating the radioactive waste liquid, firstly, the radioactive waste liquid is subjected to flocculation precipitation treatment, so that impurities in the radioactive waste liquid are primarily removed, a supernatant after precipitation is obtained, and the influence of the impurities in the radioactive waste liquid on the subsequent freeze concentration treatment effect is reduced. And then pre-cooling the supernatant, reducing the temperature of the supernatant, and reducing the temperature difference between the subsequent freezing and concentrating treatment by adopting natural cold energy. And then freezing and concentrating the pre-cooled supernatant to make at least part of water in the supernatant cool 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 radioactive waste liquid is subjected to subsequent treatment. In addition, through pre-cooling treatment and then freeze concentration treatment, the radioactive waste liquid treatment efficiency can be effectively improved, and natural cold energy is adopted for freeze concentration, so that the energy consumption can be effectively reduced, and the energy conservation and the environmental protection are realized.
The system for treating the radioactive waste liquid provided by the embodiment of the application can realize the enrichment of the radionuclide in the radioactive waste liquid by utilizing the natural cold energy in the environment, effectively reduces the use of energy consumption and is simpler in system composition. The method for treating the radioactive waste liquid provided by the embodiment of the application can be applied to the system for treating the radioactive waste liquid provided by the embodiment of the application.
Drawings
The foregoing 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, in 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 system for treating radioactive waste according to an embodiment of the present application.
It should be noted that the drawings are not necessarily to scale, but are merely shown in a schematic manner that does not affect the reader's understanding.
[ Reference numerals description ]
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 apparent, the technical solutions of the present application will be clearly and completely described below with reference to the accompanying drawings of the embodiments of the present application. It will be apparent that the described embodiments are one embodiment, but not all embodiments, of the present application. All other embodiments, which can be made by a person skilled in the art without creative efforts, based on the described embodiments of the present application fall within the protection scope of the present application.
It is to be noted that unless otherwise defined, technical or scientific terms used herein should be taken in a general sense as understood by one of ordinary skill in the art to which the present application belongs. If, throughout, reference is made to "first," "second," etc., the description of "first," "second," etc., is used merely for distinguishing between similar objects and not for understanding as indicating or implying a relative importance, order, or implicitly indicating the number of technical features indicated, it being understood that the data of "first," "second," etc., may be interchanged where appropriate. If "and/or" is present throughout, it is meant to include three side-by-side schemes, for example, "A and/or B" including the A scheme, or the B scheme, or the scheme where A and B are satisfied simultaneously.
FIG. 1 is a schematic flow diagram of a method for 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 for treating radioactive waste, including: operations S101 to S104.
And S101, performing flocculation precipitation treatment on the radioactive waste liquid to obtain a supernatant after precipitation.
In operation S102, the supernatant is pre-cooled.
And S103, performing freeze concentration treatment on the pre-cooled supernatant to enable 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.
Operation S104 separates ice crystals and concentrates radioactive waste liquid.
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 so as 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, pre-cooling the supernatant obtained after flocculation and precipitation, reducing the temperature of the supernatant, and reducing the temperature difference between the supernatant and the subsequent freezing and concentrating treatment by adopting natural cold energy. And then, freezing and concentrating the pre-cooled supernatant to enable at least part of water in the supernatant to be cooled 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 subjected to subsequent treatment. Meanwhile, the crystal of the ice crystal obtained after the freeze concentration treatment is purer and complete, and radioactive substances contained in the ice crystal are reduced. In addition, the radioactive waste liquid treatment efficiency and the radioactive waste liquid treatment effect can be effectively improved by pre-cooling treatment and then freeze concentration treatment.
In addition, the processing method provided by the embodiment of the application adopts natural cold energy to carry out freeze concentration, so that the energy consumption can be effectively reduced, the environment is protected, and the damage to equipment is small. Specifically, the supernatant may be placed in an environment with a low natural temperature, and the supernatant may be concentrated by freezing in the natural low-temperature environment.
In northern areas and high-latitude areas, the outdoor temperature in winter is lower, and the method has the characteristic of larger low-temperature storage places, so that radioactive waste liquid can be frozen naturally by utilizing natural cold energy in the natural environment, enrichment of the radioactive waste liquid is realized, and 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 lower energy consumption, can remarkably save operation cost and has lower equipment requirement.
In some embodiments, the flocculation precipitation treatment comprises: one or more flocculating agents are added into the radioactive waste water to realize flocculation precipitation of impurities in the radioactive waste water, reduce the existence of the impurities and reduce the influence of the impurities on the subsequent freeze concentration treatment.
In some embodiments, the radioactive waste may be flocculated using at least one of hydroxide precipitation, phosphate precipitation, and manganese salt flocculation precipitation. The flocculant used in the present embodiment may be at least one of hydroxide, aluminum salt, iron salt, phosphate, and manganese salt. Wherein, the aluminum salt can be polyaluminum chloride, polyaluminum sulfate, polyaluminum phosphate and the like; the ferric salt can be polymeric ferric sulfate, ferric trichloride, ferrous sulfate and the like; the phosphate can be ammonium phosphate; manganese chloride and manganese sulfate can be selected as manganese salt. In some embodiments, materials such as natural polymer modified polyacrylamide can also be selected as flocculant.
In some embodiments, the radioactive waste may be subjected to a flocculation precipitation treatment using a flocculation precipitation tank. Specifically, the radioactive waste is placed in a flocculation precipitation tank, and then a flocculant is added to the flocculation precipitation tank to flocculate and precipitate impurities in the radioactive waste.
In operation S102, the supernatant may be pre-cooled using natural cooling energy. Specifically, the supernatant may be placed in a natural low temperature environment, such as an outdoor environment in winter in northern areas or high latitude areas. In northern areas and high-latitude areas, the outdoor temperature is lower in winter, and the environment-friendly solar energy radioactive waste water storage device has a large low-temperature storage place, so that radioactive waste water can be frozen naturally by utilizing natural cold energy in the natural environment, the enrichment of 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 lower energy consumption, can remarkably save operation cost and has lower equipment requirement.
In some embodiments, the supernatant may be pre-cooled using a pre-cooling tank. Specifically, 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 the pre-cooling tank using a radioactive waste liquid transfer device. Wherein the radioactive waste liquid conveying device can be a pump.
Further, after the formation of the ice crystals, the supernatant may be pre-cooled with water after the melting of the ice crystals. In the embodiment, water formed after the ice crystals are melted is used as cold energy for precooling supernatant fluid, so that the energy consumption in the precooling treatment process can be effectively reduced, the recycling of the ice crystal wastewater can be realized, and the discharge of the wastewater is reduced.
In this embodiment, heat exchange is performed between water formed by melting ice crystals and the supernatant to pre-cool the supernatant, thereby achieving energy saving. Specifically, a heat exchanger can be arranged in the pre-cooling tank, water formed after the ice crystals are melted is conveyed into the heat exchanger, and the heat exchange is carried out on the water formed by the melting of the ice crystals and the supernatant fluid by using the heat exchanger so as to absorb the heat of the supernatant fluid, so that the pre-cooling of the supernatant fluid is realized.
Alternatively, the separated ice crystal can 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 can convey water formed by melting the ice crystal in the ice crystal storage tank to the heat exchanger so as to pre-cool the supernatant. The heat-exchanged water can be conveyed back to the ice crystal storage tank through the conveying device so as to exchange heat with the ice crystals in the ice crystal storage tank, and melting of the ice crystals is realized. In this embodiment, the conveying device may be a water pump, so that water formed by melting ice crystals is pumped to the heat exchanger.
In some embodiments, the supernatant may be pre-chilled at a cooling temperature of 0 ℃ to 5 ℃ and may also be cooled at a cooling temperature of 5 ℃ to 10 ℃. When the cooling temperature of the supernatant precooling treatment is larger than the temperature of the freeze concentration treatment, the system energy consumption is higher, the freeze concentration treatment time is longer, and the purity of the ice crystal body in the freeze concentration treatment process is not high. Therefore, the cooling temperature of the supernatant pre-cooling treatment is preferably 0 to 5 ℃ in view of the economical cost, time and the effect of the radioactive waste liquid concentration. The time of the pre-cooling treatment is determined according to the volume of the supernatant and the temperature of the pre-cooling treatment, and it should be noted that the pre-cooling treatment temperatures are shown in the present embodiment for illustration only.
In operation S104, after the formed ice crystals account for 30% -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 formed ice crystals account for 30%, 50%, 60%, 70%, 80%, 90% of the volume of the pre-cooled supernatant, and the like. In the volume ratio range, the obtained ice crystals are purer, the contained radioactive substances are less, and the concentration of the obtained concentrated radioactive waste liquid can reach 5-10 times of the concentration 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 concentrates are employed, the concentration of the concentrated radioactive waste may be further increased, for example, to enable the concentration of the resulting concentrated radioactive waste to be about 15-20 times the concentration of the radioactive waste without freeze concentration, thereby indicating that the radioactive waste can be effectively enriched by way of pre-chilling and freeze concentration.
Further, the ice crystals and the concentrated radioactive waste liquid can be separated 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 at which the pre-cooled supernatant is subjected to the freeze concentration process in operation S103 may be-5 ℃ to-25 ℃, e.g., -25 ℃, -10 ℃, -5 ℃, etc. Can also be operated at higher altitudes and in extreme winter, such as-30 ℃, -40 ℃ and the like.
Further, the pre-set time for performing freeze concentration treatment on the pre-cooled supernatant may be 4h-70h, for example, may be 4h, 10h, 15h, 30h, 50h, 70h, etc. The time for freeze concentration may be determined according to the volume of the supernatant, the temperature of the natural environment, and the temperature difference between the pre-cooling treatment and 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, freezing concentration has less energy consumption, less damage to equipment and no need of additional heat exchange equipment, and reduces the cost. And the water obtained after the ice crystal is melted can be recycled, so that the discharge of wastewater is reduced. In addition, the radioactive waste liquid treatment is an uninterrupted process, and in long-term development, a low-carbon environment-friendly mode is needed for treatment.
In some embodiments, the pre-cooled supernatant may be transferred to a freeze concentration tank to freeze concentrate the supernatant. When separating the frozen ice crystal and the concentrated radioactive waste liquid, the concentrated radioactive waste liquid in the freezing and concentrating tank can be discharged, and then the ice crystal is transferred out of the freezing and concentrating tank, so that the radioactive waste liquid polluted on the surface of the ice crystal is reduced.
Specifically, can set up the liquid outlet at freezing concentration tank bottom, the top sets up the export, sets up the filter screen that can reciprocate in the freezing concentration tank. During separation, the liquid outlet at the bottom of the freezing and concentrating tank is opened first to discharge the concentrated radioactive waste liquid, and then the filter screen is controlled to move upwards from the bottom to the top of the freezing and concentrating tank so as to transfer the ice crystals in the freezing and concentrating tank out of the outlet.
In some embodiments, the surface of the ice crystal can be washed before the ice crystal is transferred, so that the residue of the concentrated radioactive waste liquid on the surface of the ice crystal can be effectively reduced, and the concentration of radioactive substances in water after the ice crystal is melted can be reduced.
The embodiment of the application also provides a system for treating radioactive waste liquid, which adopts the method for treating radioactive waste liquid in the embodiment to treat radioactive waste liquid. Wherein, this system includes: a raw liquid tank, a flocculation precipitation tank, a pre-cooling tank and a freezing concentration tank.
Wherein, the stock solution jar 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 a supernatant after precipitation. The precooling tank is connected with the flocculation precipitation tank and is used for receiving supernatant and carrying out precooling treatment on the supernatant. The freezing and concentrating tank is connected with the pre-cooling tank and is used for receiving the pre-cooled supernatant and carrying out freezing and concentrating treatment on the pre-cooled supernatant, so that at least part of water in the supernatant is cooled 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 from natural cold energy in the environment.
Fig. 2 is a schematic diagram of a system for treating radioactive waste according to an embodiment of the present application. The system for treating radioactive waste will be described in detail with reference to fig. 2. As shown in fig. 2, the system for treating radioactive waste liquid includes a raw liquid tank 1, a flocculation precipitation tank 2, a pre-cooling tank 3 and a freeze concentration tank 4.
In some embodiments, the stock solution tank 1 is used to store radioactive waste solution. The top of the stock solution jar 1 is provided with the delivery port, and the top of flocculation precipitation jar 2 is provided with the water inlet, and this water inlet is linked together with the delivery port of stock solution jar 1 to in transferring the radioactive waste liquid in the stock solution jar 1 to flocculation precipitation jar 2, flocculation precipitation jar 2 can receive the radioactive waste liquid in order to carry out flocculation precipitation to the radioactive waste liquid and handle, so that get rid of the impurity in the radioactive waste liquid.
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 precipitation tank 2, and can suck the radioactive waste liquid in the raw liquid tank 1 into the flocculation precipitation tank 2. After the radioactive waste is transferred to the flocculation precipitation tank 2, a flocculant may be added to the flocculation precipitation tank 2 to flocculate and precipitate impurities in the radioactive waste. After flocculation precipitation treatment, the radioactive waste liquid is layered, and supernatant and impurity precipitate of the lower layer are obtained.
Further, the supernatant may be subjected to a pre-cooling treatment using a pre-cooling tank 3. The supernatant formed after flocculation precipitation may be transferred to the pre-cooling tank 3 for pre-cooling in the pre-cooling tank 3. In some embodiments, the top of flocculation precipitation tank 2 is provided with a water outlet, the top of pre-cooling tank 3 is provided with a water inlet, which is connected with the water outlet at the top of flocculation precipitation tank 2 to transfer the radioactive waste liquid in flocculation precipitation tank 2 into pre-cooling tank 3, and pre-cooling tank 3 can receive the supernatant to pre-cool 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, so that the supernatant in the flocculation precipitation tank 2 can be pumped into the pre-cooling tank 3. Wherein the supernatant conveying means may be a pump.
In this embodiment, the pre-cooled supernatant may be transferred to the freeze concentration tank 4 to perform freeze concentration treatment on the supernatant. Specifically, a water inlet may be disposed at the top of the freeze concentration tank 4, a water outlet may be disposed at the top of the pre-cooling tank 3, the water inlet of the freeze concentration tank 4 is connected with the water outlet of the pre-cooling tank 3, so as to transfer the supernatant in the pre-cooling tank 3 into the freeze concentration tank 4, the freeze concentration tank 4 may receive the pre-cooled supernatant and perform freeze 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. Wherein the cold energy used by the freeze concentration tank 4 is from natural cold energy in the environment.
In some embodiments, a supernatant conveying device is provided between the water inlet of the freeze concentration tank 4 and the water outlet of the pre-cooling tank 3, which can be used to pump supernatant in the pre-cooling tank 3 into the freeze concentration tank 4. The supernatant conveying means may be a pump, for example.
In some embodiments, the bottom of the freeze concentration tank 4 is provided with a liquid outlet for discharging concentrated radioactive waste liquid in the freeze concentration tank 4 to effect separation between ice crystals and concentrated radioactive waste liquid.
As shown in fig. 2, in some embodiments, the system for treating radioactive waste further includes 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 concentration jar 4 bottom to in transferring the concentrated radioactive waste liquid in the freezing concentration jar 4 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 also provided within the freeze concentration tank 4, the filter screen 7 being configured to move up and down within the freeze concentration tank 4 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 begins.
In performing 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 the water in the freezing and concentrating tank 4 is frozen to form ice crystals, and the ice crystals 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 freeze concentration tank 4. And concentrated radioactive waste liquid can flow from the filter screen 7 to the bottom of the freezing and concentrating tank 4, so that separation of ice crystals and the concentrated radioactive waste liquid is realized.
In some embodiments, when it is desired to separate ice crystals and concentrate radioactive waste, the concentrated radioactive waste may be discharged from the outlet at the bottom of the freeze concentration tank 4 and then the filter screen 7 is controlled to move upward to remove ice crystals from the outlet at the top of the freeze concentration tank 4.
Alternatively, the surface of the ice crystals may be rinsed with water prior to the transfer of the ice crystals, whereby radioactive waste liquid contaminated on the surface of the ice crystals is removed, and the rinsed ice crystals are transferred out of the freeze concentration tank 4. Before flushing, the filter screen 7 can be moved upwards for a certain distance, so that a space is reserved between the ice crystal and the bottom of the freeze concentration tank 4, and the flushed water can flow down from the ice crystal and the filter screen 7, so that the water containing radioactive substances after flushing is prevented from remaining on the ice crystal. In this embodiment, the rinsed water may be retained in the freeze concentration tank 4 for freeze concentration treatment with the subsequent radioactive 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 the separated ice crystals. Specifically, the top of ice crystal storage tank 5 is provided with an inlet connected to an outlet provided at the top of freeze concentration tank 4, so that the ice crystals in freeze concentration tank 4 can be transferred into ice crystal storage tank 5. Optionally, a transfer 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, which can transfer ice crystals to the ice crystal storage tank 5. In addition, the ice crystals in the present embodiment are in the form of a block, and the ice crystals may 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 the supernatant liquid in the pre-cooling tank 3 so as to absorb heat of the supernatant liquid, and the water after heat exchange can be conveyed back to 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 to form water, thereby realizing reciprocating circulation.
In some embodiments, a delivery device 9 may be provided in ice crystal storage tank 5 to efficiently deliver water formed by melting ice crystals in ice crystal storage tank 5 to heat exchanger 8. The conveying means 9 may be a suction pump. In addition, the heat exchanger 8 may be a serpentine tube in structure, thereby increasing the heat exchange area and improving the pre-cooling efficiency.
In this embodiment, the stock solution tank 1, the flocculation precipitation tank 2, the pre-cooling tank 3, the freeze concentration tank 4, the ice crystal storage tank 5 and the concentrate storage tank 6 in the radioactive waste liquid treatment system are all provided with shielding layers so as to avoid radiation of the radioactive waste liquid to other equipment and the environment. The shielding layer can be made of lead, 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 the stainless steel tank body, so that the damage of radioactive waste liquid to people or the environment is reduced. A shielding device, such as a radiation-proof box, can also be arranged on the outer covers of the raw liquid 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 liquid storage tank 6. In addition, the tank body and the tank body can be connected in a pipe connection mode, and the used pipe also has the function of radiation protection.
The system for treating radioactive waste liquid in the embodiment of the application has the following specific steps in the radioactive waste liquid treatment process:
And pumping the radioactive waste liquid stored in the raw liquid tank 1 into a flocculation precipitation tank 2 by a pump to perform flocculation precipitation, and obtaining 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 pre-cooling temperature is 0-5 ℃. And pumping the pre-cooled supernatant into a freezing and concentrating tank 4 for freezing and concentrating treatment, so that at least part of water in the supernatant is cooled to form ice crystals, and the rest liquid is concentrated to form concentrated radioactive waste liquid. Wherein, the cold energy of the freeze concentration treatment is from natural cold energy in the environment.
When the volume of the formed ice crystals accounts for 30% -90% of the volume of the supernatant liquid after precooling, the ice crystals can be separated and the radioactive waste liquid can be concentrated. The bottom of the freezing and concentrating tank 4 is provided with a liquid outlet through which concentrated radioactive waste liquid in the freezing and concentrating tank 4 can be discharged. The top of concentrate storage tank 6 is equipped with the inlet, and this inlet is connected with the liquid outlet of freezing concentration tank 4 bottom, and concentrate storage tank 6 is used for receiving and storing 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 ice crystals can be removed from the outlet in the freeze concentration tank 4 by moving the filter screen 7 upwards after concentrated radioactive waste liquid is discharged and transferred to the ice crystal storage tank 5 to store the separated ice crystals.
The water formed by melting the ice crystals in the ice crystal storage tank 5 is conveyed into the heat exchanger 8 through the conveying device 9, and the heat exchanger 8 exchanges heat between the water formed by melting the ice crystals and the supernatant fluid, so that the pre-cooling treatment of the supernatant fluid is realized. The heat-exchanged water 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 circulates reciprocally. During the treatment process, all the operation processes are subjected to radiation protection treatment, so that the harm of radioactive substances to people or the environment is avoided.
In some embodiments, to achieve a deeper level of treatment of the radioactive waste, multiple systems for treating the radioactive waste may be connected in series to further increase the concentration of the radioactive waste.
The technical scheme of the present application will be clearly and completely described in the following in connection with specific embodiments. It will be apparent that the described embodiments are one embodiment, but not all embodiments, of the present application.
Example 1
Firstly, pumping the radioactive wastewater in the raw solution tank into a flocculation precipitation tank, and performing flocculation precipitation by using a polyaluminium chloride flocculant to primarily remove part of impurities in the radioactive wastewater so as to obtain a 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 and concentrating tank for freezing and concentrating, so that at least part of water in the supernatant is cooled to form ice crystals, and concentrating the residual liquid to form concentrated radioactive waste liquid, wherein the cold energy of freezing and concentrating treatment is natural cold energy in the environment, the freezing and concentrating temperature is-13 ℃, and the freezing and concentrating time is 6 hours.
And fourthly, separating the ice crystals formed by freezing and concentrating and the concentrated radioactive waste liquid, and transferring the ice crystals to an ice crystal storage tank for storage. 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 method comprises the steps of melting ice crystals in an ice crystal storage tank to form water, conveying the water formed by melting the ice crystals into a heat exchanger of a pre-cooling tank through a conveying device (a water suction pump), pre-cooling supernatant by adopting the heat exchanger, and pumping the water formed by melting the ice crystals back into the ice crystal storage tank through the water suction pump after heat exchange to melt the ice crystals.
Example 2
The process of freezing and concentrating radioactive wastewater comprises 4 steps:
Firstly, pumping the radioactive wastewater in the raw liquid tank into a flocculation precipitation tank, adding chemical reagent ammonium phosphate as a flocculant for flocculation precipitation, and primarily removing partial impurities in the radioactive wastewater.
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 precooled supernatant into a freezing and concentrating tank for freezing and concentrating, so that at least part of water in the supernatant is cooled to form ice crystals, and the rest 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-18 ℃, and the freeze concentration time is 4 hours.
And fourthly, separating the ice crystals formed by freezing and concentrating from the concentrated radioactive waste liquid, and transferring the ice crystals to an ice crystal storage tank for storage through an outlet formed at the top of the freezing and concentrating tank. And transferring the concentrated radioactive waste liquid to a concentrated liquid tank for storage through a water outlet formed in the bottom of the freezing concentration tank, increasing the concentration of radioactive substances in the concentrated radioactive waste liquid, and transferring to the next process for subsequent treatment.
The method comprises the steps of carrying out heat exchange on ice crystals in an ice crystal storage tank to form water, conveying the water formed by melting the ice crystals into a heat exchanger in a pre-cooling tank through a conveying device (a water suction pump), carrying out pre-cooling treatment on supernatant by adopting the heat exchanger, and pumping the water formed by melting the ice crystals back into the ice crystal storage tank through the water suction pump after heat exchange to melt the ice crystals.
Example 3
The process of freezing and concentrating radioactive wastewater comprises 4 steps:
Firstly, pumping the radioactive wastewater in the raw liquid tank into a flocculation precipitation tank, adding chemical reagent ammonium phosphate as a flocculant for flocculation precipitation, and primarily removing partial impurities in the radioactive wastewater.
And secondly, pumping the supernatant in the flocculation precipitation tank into a pre-cooling tank, and pre-cooling the supernatant to 5 ℃ to obtain pre-cooled supernatant.
And thirdly, pumping the precooled supernatant into a freezing and concentrating tank for freezing and concentrating, so that at least part of water in the supernatant is cooled to form ice crystals, and the rest liquid is concentrated to form concentrated radioactive waste liquid. The cold energy of the freezing and concentrating treatment is natural cold energy in the environment, the freezing and concentrating temperature is-10 ℃, the freezing and concentrating time is 20 hours, and the formed ice crystals account for 90% of the volume of the pre-cooled supernatant.
And fourthly, separating the frozen and concentrated ice crystals and the concentrated radioactive waste liquid, and transferring the ice crystals into an ice crystal storage tank for storage through an outlet formed at the top of the frozen and concentrated tank. The method comprises the steps of carrying out heat exchange on ice crystals in an ice crystal storage tank to form water, conveying the water formed by melting the ice crystals into a heat exchanger in a pre-cooling tank through a conveying device (a water suction pump), carrying out pre-cooling treatment on supernatant by adopting the heat exchanger, and pumping the water formed by melting the ice crystals back into the ice crystal storage tank through the water suction pump after heat exchange 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 arranged at 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 of freezing and concentrating radioactive wastewater comprises 4 steps:
Firstly, pumping the radioactive wastewater in the raw liquid tank into a flocculation precipitation tank, adding chemical reagent ammonium phosphate as a flocculant for flocculation precipitation, and primarily removing partial impurities in the radioactive wastewater.
And secondly, pumping the supernatant in the flocculation precipitation tank into a pre-cooling tank, and pre-cooling the supernatant to 0-5 ℃ to obtain pre-cooled supernatant.
And thirdly, pumping the precooled 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 rest liquid is concentrated to form concentrated radioactive waste liquid, wherein the cold energy of freezing and concentrating treatment is natural cold energy in the environment, the freezing and concentrating temperature is-18 to-13 ℃, and the freezing and concentrating time is 4-30h.
Fourth, when the volume of the formed ice crystals accounts for 60% of the volume of the pre-cooled supernatant, separating the ice crystals formed by freeze concentration and concentrating radioactive waste liquid. And (3) moving the ice crystals to the tank opening of the freezing concentration tank through the filter screen, and transferring the ice crystals to an adjacent ice crystal storage tank for storage through an outlet formed in the top of the freezing concentration tank. The surface flushing of the ice crystals may also be performed prior to their transfer to remove concentrated radioactive liquid from surface contaminants, the liquid flushing the ice crystals remaining in the freeze concentration tank. And transferring the concentrated radioactive waste liquid to a concentrated liquid tank for storage through a water outlet formed in the bottom of the freezing concentration tank, increasing the concentration of radioactive substances in the concentrated radioactive waste liquid, and transferring to the next process for subsequent treatment.
In addition, the ice crystals in the ice crystal storage tank are melted to form water after heat exchange, the water formed by melting the ice crystals is conveyed to a heat exchanger in the pre-cooling tank through a conveying device (a water suction pump), the supernatant is subjected to pre-cooling treatment 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 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 the embodiments, but the present invention is not limited to the embodiments described above, 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 invention may be practiced otherwise than as specifically described.
Claims (13)
1. A method of treating radioactive waste comprising:
flocculating and precipitating the radioactive waste liquid to obtain a supernatant after precipitation;
Pre-cooling the supernatant;
freezing and concentrating the pre-cooled supernatant to make at least part of water in the supernatant form ice crystals, and concentrating the rest 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 radioactive waste liquid after the formed ice crystals account for 30-90% of the volume of the pre-cooled supernatant;
transferring the pre-cooled supernatant to a freeze concentration tank to freeze concentrate the supernatant, so that at least part of water in the supernatant is cooled to form massive ice crystals;
the bottom of the freezing and concentrating tank is provided with a liquid outlet, the top of the freezing and concentrating tank is provided with an outlet, and a filter screen is arranged in the freezing and concentrating tank and can move up and down in the freezing and concentrating tank;
Said separating said ice crystals and concentrating radioactive waste liquid in said freeze concentration tank comprising:
Opening the liquid outlet, and discharging the concentrated radioactive waste liquid in the freezing and concentrating tank;
Controlling the filter screen 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;
Further comprises: and before the ice crystals are transferred, the filter screen is moved upwards from the bottom of the freezing and concentrating tank, so that a space is reserved between the ice crystals and the bottom of the freezing and concentrating tank, and the surface of the ice crystals is washed.
2. The method of claim 1, wherein the flocculation precipitation treatment comprises: adding one or more flocculants to the radioactive waste;
the flocculant comprises: at least one of aluminum salt, ferric salt, phosphate and manganese salt.
3. The method of claim 1, wherein the supernatant is pre-cooled using natural cooling energy.
4. A method according to claim 3, wherein the pre-cooling treatment is performed on the supernatant liquid with water after melting of the ice crystals, after the ice crystals have been formed.
5. The method of claim 4, wherein the step of determining the position of the first electrode is performed,
Transferring the supernatant to a pre-cooling tank, wherein a heat exchanger is arranged in the pre-cooling tank;
And conveying 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 radioactive waste concentrated after the supernatant is frozen at a predetermined temperature for a predetermined time.
7. A system for treating radioactive waste, characterized in that it implements a treatment of said radioactive waste with a method according to any one of claims 1-6, 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 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 and concentrating tank is connected with the pre-cooling tank and is used for receiving the pre-cooled supernatant and carrying out freezing and concentrating treatment on the supernatant so that at least part of water in the supernatant is frozen to form ice crystals, and the rest liquid is concentrated to form concentrated radioactive waste liquid;
Wherein the cold energy used by the freezing and concentrating tank is from natural cold energy in the environment.
8. The system of claim 7, wherein a bottom of the freeze concentration tank is provided with a liquid outlet for discharging concentrated radioactive waste liquid from the freeze concentration tank.
9. The system of claim 8, 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 concentration tank bottom is connected, the concentrated solution storage tank is used for receiving and storing concentrated radioactive waste liquid.
10. The system of claim 8, wherein the system further comprises a controller configured to control the controller,
An outlet is formed in the top of the freezing concentration tank;
A filter screen is disposed within the freeze concentration tank and is configured to move up and down within the freeze concentration tank for removing the ice crystals from the outlet.
11. The system of claim 7, further comprising:
And the ice crystal storage tank is connected with the freezing concentration tank and is used for storing the separated ice crystals.
12. The system of claim 11, wherein the system further comprises a controller configured to control the controller,
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 conveying device is used for conveying 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.
13. The system according to any one of claims 7-12, wherein the stock solution tank, flocculation precipitation tank, pre-cooling tank and 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 |
|---|
| 碱性铀沉淀母液治理新工艺;黄昌海, 许道铭, 刘尚勇, 周丽华, 张依群, 杨宏, 赵有君;铀矿冶;第20卷(第1期);第35-41页 * |
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