CN115487602A - System and method for separating insoluble solid in triuranium octoxide dissolving solution - Google Patents
System and method for separating insoluble solid in triuranium octoxide dissolving solution Download PDFInfo
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- CN115487602A CN115487602A CN202211268611.5A CN202211268611A CN115487602A CN 115487602 A CN115487602 A CN 115487602A CN 202211268611 A CN202211268611 A CN 202211268611A CN 115487602 A CN115487602 A CN 115487602A
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- 239000007787 solid Substances 0.000 title claims abstract description 30
- 229910000442 triuranium octoxide Inorganic materials 0.000 title claims abstract description 30
- 238000000034 method Methods 0.000 title claims abstract description 20
- 239000007788 liquid Substances 0.000 claims abstract description 119
- 239000002893 slag Substances 0.000 claims abstract description 51
- 238000000926 separation method Methods 0.000 claims abstract description 36
- IQWPWKFTJFECBS-UHFFFAOYSA-N O=[U](=O)O[U](=O)(=O)O[U](=O)=O Chemical compound O=[U](=O)O[U](=O)(=O)O[U](=O)=O IQWPWKFTJFECBS-UHFFFAOYSA-N 0.000 claims abstract description 9
- 239000000243 solution Substances 0.000 claims description 68
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 68
- 239000002245 particle Substances 0.000 claims description 33
- 238000004140 cleaning Methods 0.000 claims description 15
- 238000007789 sealing Methods 0.000 claims description 12
- 230000001105 regulatory effect Effects 0.000 claims description 10
- 238000005406 washing Methods 0.000 claims description 10
- 238000009826 distribution Methods 0.000 claims description 6
- 238000001914 filtration Methods 0.000 claims description 6
- 239000011521 glass Substances 0.000 claims description 6
- 239000011550 stock solution Substances 0.000 claims description 6
- 239000000126 substance Substances 0.000 claims description 4
- 238000005119 centrifugation Methods 0.000 claims 2
- 238000004891 communication Methods 0.000 claims 1
- 238000002203 pretreatment Methods 0.000 claims 1
- 238000000605 extraction Methods 0.000 description 11
- 239000012535 impurity Substances 0.000 description 10
- 239000002994 raw material Substances 0.000 description 8
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 7
- 229910017604 nitric acid Inorganic materials 0.000 description 7
- 229910052770 Uranium Inorganic materials 0.000 description 6
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 6
- 229910002007 uranyl nitrate Inorganic materials 0.000 description 6
- 238000004519 manufacturing process Methods 0.000 description 5
- 229910052751 metal Inorganic materials 0.000 description 5
- 239000002184 metal Substances 0.000 description 5
- 239000000463 material Substances 0.000 description 4
- 239000011148 porous material Substances 0.000 description 4
- 238000000746 purification Methods 0.000 description 4
- 238000003860 storage Methods 0.000 description 4
- 239000000706 filtrate Substances 0.000 description 3
- 238000011010 flushing procedure Methods 0.000 description 3
- 239000002699 waste material Substances 0.000 description 3
- 230000000903 blocking effect Effects 0.000 description 2
- 239000008367 deionised water Substances 0.000 description 2
- 229910021641 deionized water Inorganic materials 0.000 description 2
- 238000000151 deposition Methods 0.000 description 2
- 238000007599 discharging Methods 0.000 description 2
- 230000005484 gravity Effects 0.000 description 2
- 239000013049 sediment Substances 0.000 description 2
- 238000004062 sedimentation Methods 0.000 description 2
- 150000003384 small molecules Chemical class 0.000 description 2
- 229910002651 NO3 Inorganic materials 0.000 description 1
- NHNBFGGVMKEFGY-UHFFFAOYSA-N Nitrate Chemical compound [O-][N+]([O-])=O NHNBFGGVMKEFGY-UHFFFAOYSA-N 0.000 description 1
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N Silicium dioxide Chemical compound O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 description 1
- WZECUPJJEIXUKY-UHFFFAOYSA-N [O-2].[O-2].[O-2].[U+6] Chemical compound [O-2].[O-2].[O-2].[U+6] WZECUPJJEIXUKY-UHFFFAOYSA-N 0.000 description 1
- 239000002253 acid Substances 0.000 description 1
- 239000003513 alkali Substances 0.000 description 1
- 238000003491 array Methods 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000005540 biological transmission Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 239000012141 concentrate Substances 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000006185 dispersion Substances 0.000 description 1
- 238000004090 dissolution Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 239000013072 incoming material Substances 0.000 description 1
- RSMUVYRMZCOLBH-UHFFFAOYSA-N metsulfuron methyl Chemical compound COC(=O)C1=CC=CC=C1S(=O)(=O)NC(=O)NC1=NC(C)=NC(OC)=N1 RSMUVYRMZCOLBH-UHFFFAOYSA-N 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 150000002823 nitrates Chemical class 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- -1 salt ion Chemical class 0.000 description 1
- 239000000741 silica gel Substances 0.000 description 1
- 229910002027 silica gel Inorganic materials 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
- 229910000439 uranium oxide Inorganic materials 0.000 description 1
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Classifications
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01D—SEPARATION
- B01D36/00—Filter circuits or combinations of filters with other separating devices
- B01D36/04—Combinations of filters with settling tanks
- B01D36/045—Combination of filters with centrifugal separation devices
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- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Centrifugal Separators (AREA)
Abstract
The invention provides a system and a method for separating insoluble solids from triuranium octoxide dissolved solution. The invention discloses a system for separating indissolvable solids in triuranium octoxide dissolving liquid, which comprises a pretreatment system and a centrifugal separation system, wherein the pretreatment system comprises a filter, the centrifugal separation system comprises a disc centrifuge, the filter and the disc centrifuge are respectively provided with a liquid inlet, a liquid outlet and a slag outlet, a coarse filter screen and a fine filter screen are sequentially arranged in the filter, the liquid inlet and the liquid outlet of the filter are respectively positioned at the positions of the coarse filter screen and the fine filter screen, the disc centrifuge is provided with a rotary drum part, a plurality of discs are arranged in the rotary drum part, the liquid inlet of the disc centrifuge is arranged on the rotary drum part, and the liquid outlet of the filter is communicated with the liquid inlet of the disc centrifuge. The system and the method can effectively remove insoluble solids in the uranium octoxide dissolved solution, and greatly reduce the problems of scaling and blockage of rear-end equipment through which the dissolved solution flows.
Description
Technical Field
The invention relates to the technical field of solid-liquid separation, in particular to a system and a method for separating insoluble solids in triuranium octoxide dissolved solution.
Background
The method is characterized in that a natural triuranium octoxide raw material used in a natural uranium purification production line is a key raw material of the process, triuranium octoxide reacts with dilute nitric acid to generate uranyl nitrate solution, and the dilute nitric acid is excessive in the reaction process, so that the generated uranyl nitrate solution contains about 1mol/L of nitric acid. Meanwhile, because the natural triuranium octoxide raw material of the uranium ore concentrate contains metal impurities, the dissolved uranyl nitrate solution obtained by dissolution needs to be purified through the processes of extraction, washing and back extraction so as to remove the metal impurities such as K, na, ca, mg, fe, cr, mo and the like, and the adopted equipment is usually a baffle plate pulse column and a sieve plate pulse column. The extraction process can generate a large amount of raffinate which contains a large amount of unextracted metal salt ion impurities, residual metal uranium and nitric acid with a certain concentration, most of the nitric acid and water in the raffinate are recovered through equipment such as a reduced pressure rectifying tower, a reboiler and the like, and the rest of the non-volatile components such as metal impurities, nitrates and the like are concentrated in a rectifying tower kettle and a tubular reboiler of a nitric acid recovery rectifying tower in a rectifying tower residue form after being concentrated, wherein the concentration multiple is up to 30 times.
In the technical process, if insoluble solids in triuranium octoxide solution are not removed and directly flow into an extraction-washing-back extraction operation unit, the insoluble solids enter a baffle plate pulse extraction column along with the solution, are easy to attach to the surface of a baffle plate in the extraction column to cause scaling, are not beneficial to two-phase dispersion flow in the extraction column, and cause reduction of extraction efficiency. In addition, after the dissolved solution is extracted, a large amount of insoluble solids can remain in the raffinate, and the reboiler is easy to block after the insoluble solids are concentrated by a tubular reboiler. In actual production, the raw materials need to be selected according to the incoming material condition of the natural triuranium octoxide and then put into use, so that the problems that part of the raw materials cannot be used and the like are caused. Therefore, it is necessary to develop a separation method for separating a sparingly soluble solid from a triuranium octoxide dissolved solution.
In view of this, the invention is particularly proposed.
Disclosure of Invention
The invention aims to provide a system and a method for separating insoluble solids in a uranium octoxide dissolved solution, which can effectively remove the insoluble solids in the uranium octoxide dissolved solution and greatly reduce the problems of scaling and blockage of rear-end equipment through which the dissolved solution flows.
The invention provides a system for separating indissolvable solids in triuranium octoxide dissolving liquid, which comprises a pretreatment system and a centrifugal separation system, wherein the pretreatment system comprises a filter, the centrifugal separation system comprises a disc centrifuge, the filter and the disc centrifuge are respectively provided with a liquid inlet, a liquid outlet and a slag outlet, a coarse filter screen and a fine filter screen are sequentially arranged in the filter, the liquid inlet and the liquid outlet of the filter are respectively positioned at the positions of the coarse filter screen and the fine filter screen, the disc centrifuge is provided with a rotary drum part, a plurality of discs are arranged in the rotary drum part, the liquid inlet of the disc centrifuge is arranged on the rotary drum part, and the liquid outlet of the filter is communicated with the liquid inlet of the disc centrifuge.
Further, the filtration precision of the filter is 200 μm; the filter is a self-cleaning filter provided with a cleaning part for cleaning a coarse filter screen and a fine filter screen.
Furthermore, the pretreatment system also comprises a stock solution tank for storing the triuranium octoxide solution, the stock solution tank is communicated with the liquid inlet of the filter through a liquid inlet pipe, and the liquid inlet pipe is provided with a liquid supply pump, a flow meter and an electric regulating valve.
Further, pretreatment systems still includes the first slag chute that is used for depositing the filter residue, and the slag notch of filter is equipped with the sediment solenoid valve on the pipe of slagging tap through slag pipe and first slag chute intercommunication.
Further, pretreatment systems still includes the transfer cistern of setting between filter and disk centrifuge, and the transfer cistern has inlet, liquid outlet and gas vent, and the inlet of transfer cistern and the liquid outlet of filter intercommunication, the liquid outlet of transfer cistern pass through feed liquor pipe and disk centrifuge's inlet intercommunication, are equipped with feed liquor pump, flowmeter and electrical control valve on the feed liquor pipe.
Furthermore, the centrifugal separation system also comprises an operation water tank, wherein a sealing water inlet, a washing water inlet and a slag discharge water inlet are arranged on the disc centrifuge, the operation water tank is respectively communicated with the sealing water inlet, the washing water inlet and the slag discharge water inlet through a main water outlet pipe and three water distribution pipes, an operation water pump is arranged on the main water outlet pipe, and electromagnetic valves are respectively arranged on the three water distribution pipes.
Furthermore, the centrifugal separation system also comprises a second slag groove for storing filter residues of the disc centrifuge, and the second slag groove is connected with a slag outlet of the disc centrifuge through an outer ring valve type automatic slag discharging device.
Furthermore, sight glasses are respectively arranged at the liquid inlet and the liquid outlet of the disk centrifuge; a pressure meter and a manual pressure regulating valve are arranged on the liquid outlet pipe of the disk centrifuge.
The invention also provides a method for separating insoluble solids in the uranium octoxide dissolved solution, which is carried out by adopting the system.
Specifically, the method for separating the insoluble solid in the triuranium octoxide dissolved solution comprises the following steps:
s1: pretreating the triuranium octoxide dissolved solution by using a pretreatment system to remove large-particle substances with the particle size of more than 200 mu m to obtain a pretreatment solution;
s2: and (3) carrying out centrifugal separation on the pretreatment liquid by adopting a centrifugal separation system to remove small particles with the particle size of 10-200 mu m.
The system is provided with a pretreatment system and a centrifugal separation system, wherein the pretreatment system is provided with a filter which is mainly used for pretreating triuranium octoxide dissolving liquid to remove large particles with the particle size larger than 200 mu m; the centrifugal separation system is provided with a disk centrifuge, the disk centrifuge utilizes the principle that light phases and heavy phases which have different densities and are not mutually soluble in a dissolving solution obtain different sedimentation speeds in a centrifugal force field to achieve the purpose of separating and layering or settling solid particles in the solution, the dissolving solution with residual small particles with the particle size of 10-200 mu m enters a drum part of the disk centrifuge, the dissolving solution passes through a separation interval of a disk bundle consisting of a plurality of disks and takes a disk center hole as an interface under the action of centrifugal force, the liquid with higher specific gravity (the light phase-uranyl nitrate solution) moves outwards from the center hole along the disk wall to flow to a centripetal pump, waste residues (impurities such as heavy phase-insoluble nitric acid and the like) are accumulated in a residue settling area, the insoluble solid in the dissolving solution is well and continuously separated, the scaling and blocking problems of rear-end equipment through which the dissolving solution flows are greatly reduced, the series of baffle plates in an extraction column are reduced, the blocking risk of a reboiler is reduced, and the adaptability of a uranium purification production line to natural uranium oxide raw materials with different properties is improved.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the embodiments or the prior art will be briefly described below, and it is obvious that the drawings in the following description are some embodiments of the present invention, and other drawings can be obtained by those skilled in the art without creative efforts.
FIG. 1 is a schematic structural diagram of a system for separating a poorly soluble solid in a uranium octoxide dissolved solution according to an embodiment;
FIG. 2 is a schematic view of a portion of a filter according to an embodiment;
FIG. 3 is a schematic view of a partial structure of a disk centrifuge according to an embodiment;
fig. 4 is a schematic structural view of a liquid inlet pipe and a liquid outlet pipe of the disk centrifuge according to an embodiment.
Description of reference numerals:
1: a stock solution tank; 2: a liquid supply pump; 3: a flow meter; 4: an electric control valve; 5: a deslagging electromagnetic valve; 6: an electric brush; 7: a filter; 8: a liquid inlet; 9: an exhaust port; 10-transferring a liquid tank; 11: a liquid outlet; 12: a liquid supply pump; 13: a flow meter; 14: an electric control valve; 15: a liquid inlet; 16: a liquid outlet; 17: a disk centrifuge; 18: an outer ring valve type automatic slag discharge device; 19: a second slag groove; 20: a clear liquid receiving tank; 21: a first slag groove; 22: operating the water tank; 23: operating the water pump; 24: sealing the water electromagnetic valve; 25: a flushing water solenoid valve; 26: an electromagnetic valve of the slag discharge water; 27: a disc; 28: a slag outlet; 29: coarse filtration; 30: a fine filter screen; 31: a liquid inlet sight glass; 32: a liquid outlet sight glass; 33: a pressure gauge; 34: a manual pressure regulating valve.
Detailed Description
It should be noted that the following detailed description is exemplary and is intended to provide further explanation of the disclosure. Unless defined otherwise, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this application belongs.
It is noted that the terminology used herein is for the purpose of describing particular embodiments only and is not intended to be limiting of example embodiments according to the present application. As used herein, the singular forms also include the plural forms unless the context clearly dictates otherwise, and further, it is understood that when the terms "comprises" and/or "comprising" are used in this specification, they specify the presence of the stated features, steps, operations, devices, components, and/or combinations thereof.
The technical solutions of the present invention will be described clearly and completely with reference to the following embodiments, and it should be understood that the described embodiments are some, but not all, embodiments of the present invention. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
Example 1
Referring to fig. 1 to 4, the present embodiment provides a system for separating an insoluble solid in triuranium octoxide solution, including a pretreatment system and a centrifugal separation system, the pretreatment system includes a filter 7, the centrifugal separation system includes a disk centrifuge 17, the filter 7 has a liquid inlet, a liquid outlet and a slag outlet, the disk centrifuge 17 has a liquid inlet 15, a liquid outlet 16 and a slag outlet 28, a coarse filter screen 29 and a fine filter screen 30 are sequentially installed inside the filter 7, the liquid inlet and the liquid outlet of the filter 7 are respectively located at positions of the coarse filter screen 29 and the fine filter screen 30, the disk centrifuge 17 has a drum component, a plurality of disks 27 are installed inside the drum component, the liquid inlet 15 of the disk centrifuge 17 is disposed on the drum component, and the liquid outlet of the filter 7 is communicated with the liquid inlet 15 of the disk centrifuge 17.
The pretreatment system is mainly used for carrying out preliminary filtration on triuranium octoxide dissolved solution to remove large-particle impurities in the dissolved solution, and simultaneously, the safety operation of the subsequent centrifugal separation step is guaranteed.
The pretreatment system is provided with a filter 7, the filtering precision of the filter 7 is 200 microns, the filter 7 is made of 316L materials and is resistant to acid and alkali corrosion, and the filtering precision of the filter 7 is 200 microns, so that the pretreatment step can only remove large particles with the particle size larger than 200 microns. The major principle of the uranium octoxide dissolving solution is that the dissolving solution passes through a coarse filter screen 29 and a fine filter screen 30 in the filter 7 in sequence, large particles in the dissolving solution cannot pass through the pores of the coarse filter screen 29 and the fine filter screen 30 and are intercepted in the corresponding filter screens, and small-molecule filtrate can pass through the pores of the coarse filter screen 29 and the fine filter screen 30 and then flows out of a liquid outlet of the filter 7.
The specific structure of the filter 7 is not strictly limited, and the coarse filter mesh 29 and the fine filter mesh 30 may be provided inside the filter 7 in this order from bottom to top, for example; in addition, the filter 7 can adopt a self-cleaning filter with a self-cleaning function, the self-cleaning filter is provided with a cleaning component for cleaning the coarse filter screen 29 and the fine filter screen 30, the structure and the setting mode of the cleaning component are not strictly limited, for example, the self-cleaning filter can comprise a set of electric brushes 6 arranged in the coarse filter screen 29 and the fine filter screen 30, the electric brushes 6 are driven by a motor to rotate, during cleaning, a signal from a time switch on an electric cabinet is transmitted to a control panel, the control panel opens the slag discharge electromagnetic valve 5 and simultaneously starts the motor of the electric brushes 6, the electric brushes 6 are driven to rotate to brush off dirt impurities on the coarse filter screen 29 and the fine filter screen 30, under the action of water force, the filter 7 is discharged through a slag outlet, and cutting-off is not needed during cleaning.
It can be understood that pretreatment system can also include the stoste groove 1 that is used for depositing the triuranium octoxide solution, and stoste groove 1 is equipped with feed liquor pump 2, flowmeter 3 and electrical control valve 4 through the inlet fluid pipe and filter 7's inlet intercommunication on the feed liquor pipe, reinjects into filter 7 and carries out the preliminary treatment after the converter through feed liquor pump 2, flowmeter 3 and electrical control valve 4 control solution flow stability.
Further, the pretreatment system can also comprise a first slag groove 21 for storing filter residues of the filter 7, a slag outlet of the filter 7 is communicated with the first slag groove 21 through a slag outlet pipe, and a slag discharge electromagnetic valve 5 is arranged on the slag outlet pipe. According to the time setting, the electric brush 6 of the filter 7 and the deslagging electromagnetic valve 5 automatically open deslagging, and the filter residue of the filter 7 is conveyed to the first residue groove 21 through the deslagging pipe for temporary storage.
In addition, pretreatment systems can also be including setting up the well cistern 10 between filter 7 and disk centrifuge 17, well cistern 10 has inlet 8, liquid outlet 11 and gas vent 10, the inlet 8 of well cistern 10 and the liquid outlet intercommunication of filter 7, the liquid outlet 11 of well cistern 10 is through the inlet 15 intercommunication of feed liquor pipe with disk centrifuge 17, be equipped with liquid feed pump 12 on the feed liquor pipe, flowmeter 13 and electrical control valve 14, through the converter of liquid feed pump 12, send into disk centrifuge 17 after flowmeter 13 and electrical control valve 14 control liquid flow are stable.
The centrifugal separation system is mainly used for separating small particles of 10-200 mu m in the triuranium octoxide dissolving liquid. The centrifugal separation system is provided with a disc centrifuge 17 which mainly comprises a rotary drum part, a machine body part, a transmission part, an inlet and outlet pipeline, a vertical shaft, a transverse shaft, operating water, a safety protection device, an electrical control system and the like, wherein the disc centrifuge 17 mainly utilizes the principle that light phases and heavy phases which have different densities and are not mutually soluble in a dissolving solution obtain different sedimentation speeds in a centrifugal force field to achieve the purpose of separating and layering or settling solid particles in the liquid, the dissolving solution of small particles with the residual particle size of 10-200 mu m enters the rotary drum part of the disc centrifuge 17, under the action of centrifugal force, the dissolving solution passes through a separation interval of a disc bundle consisting of a plurality of discs 27, the liquid (light phase-uranyl nitrate solution) with larger specific gravity moves outwards along the wall of the discs 27 by taking the central hole of the discs 27 as an interface so as to flow to the central hole, waste residues (impurities such as heavy phase-insoluble nitrate) are accumulated in a sediment area, and the insoluble solids in the dissolving solution are well and continuously separated.
In the operation process of the disk centrifuge 17, sealing water, slag discharge water and flushing water need to be intermittently introduced to maintain normal operation. Therefore, the centrifugal separation system further comprises an operation water tank 22, a sealing water inlet, a washing water inlet and a slag discharge water inlet are arranged on the disk centrifuge 17, the operation water tank 22 is respectively communicated with the sealing water inlet, the washing water inlet and the slag discharge water inlet through a main water outlet pipe and three water distribution pipes, an operation water pump 23 is arranged on the main water outlet pipe, and a sealing water electromagnetic valve 24, a washing water electromagnetic valve 25 and a slag discharge water electromagnetic valve 26 are respectively arranged on the three water distribution pipes. The deionized water in the operation water tank 22 is delivered by the operation water pump 23 and enters the disc centrifuge 17 through the sealing water electromagnetic valve 24, the washing water electromagnetic valve 25 and the deslagging water electromagnetic valve 26 according to a certain program design.
Further, the centrifugal separation system further comprises a second slag groove 19 for storing filter residues of the disc centrifuge 17 and a clear liquid receiving groove 20 for storing clear liquid, the second slag groove 19 is connected with a slag outlet of the disc centrifuge 17 through an outer ring valve type automatic slag discharging device 18, and the clear liquid receiving groove 20 is communicated with a liquid outlet 16 of the disc centrifuge 17.
In addition, a liquid inlet viewing mirror 31 and a liquid outlet viewing mirror 32 are respectively arranged at the liquid inlet 15 and the liquid outlet 16 of the disc centrifuge 17; a pressure gauge 33 and a manual pressure regulating valve 34 are arranged on the liquid outlet pipe of the disk centrifuge 17.
The parts of the system for separating the insoluble solid in the uranium octoxide dissolved solution, which are selected by the system and contacted with the material, are all made of stainless steel materials, so that the chemical action of the contact surface of the separated material and the mechanical part in the separation process is effectively reduced. In addition, an adjustable centripetal pump device can be adopted, the adaptability to the feed liquid to be separated is strong, and the separation interface is easy to adjust. The PLC automatic control piston can be adopted to automatically discharge slag in the centrifugal separation process, the automatic slag discharge device has strong capability of adapting to process adjustment, high automation degree and convenient adjustment, the labor intensity of operators is relatively reduced, the requirement on the solid content of the separated liquid is wide, and the automatic slag discharge device is suitable for solid-liquid separation of solutions with different impurity contents.
The system for separating the indissolvable solid in the triuranium octoxide solution can effectively remove the indissolvable solid in the solution, greatly reduces the scaling and blockage problems of the rear-end equipment through which the solution flows, reduces the fouling on the surface of baffle plate strings in the extraction column, reduces the risk of blockage of reboiler tubes, and improves the adaptability of uranium purification production lines to natural triuranium octoxide raw materials with different properties.
Example 2
The embodiment provides a method for separating insoluble solids from a uranium octoxide dissolved solution, which is performed by using the system in embodiment 1, and comprises the following steps:
s1: pretreating the triuranium octoxide dissolved solution by using a pretreatment system to remove large-particle substances with the particle size of more than 200 mu m to obtain a pretreatment solution;
s2: and (3) carrying out centrifugal separation on the pretreatment liquid by adopting a centrifugal separation system to remove small particles with the particle size of 10-200 mu m.
Specifically, the triuranium octoxide dissolved solution in the stock solution tank 1 is delivered by a solution feed pump 2, and is injected into a filter 7 for pretreatment after the flow of the dissolved solution is controlled to be stable by a frequency converter, a flowmeter 3 and an electric regulating valve 4 of the solution feed pump 2. The lower layer of the interior of the filter 7 is provided with a coarse filter screen 29, the upper layer is provided with a fine filter screen 30, after the dissolved solution is filtered by the coarse filter screen 29 and the fine filter screen 30 in the filter 7, large particles with the particle size larger than 200 mu m can not pass through the pores of the filter screens and are intercepted in the filter screens, and the small-molecule filtrate flows out of the liquid outlet of the filter 7 through the pores of the filter screens. Large particles with the particle size larger than 200 mu m contained in the solution are filtered by a filter 7, the filtered solution flows from a liquid inlet 8 of a transit liquid tank 10 to the transit liquid tank 10 for storage, an electric brush 6 of the filter 7 and a deslagging electromagnetic valve 5 automatically open deslagging according to time setting, and the filter residue of the filter 7 is conveyed into a first residue tank 21 through a deslagging pipe for temporary storage.
The filtrate in the transit liquid tank 10 flows out from a liquid outlet 11 of the transit liquid tank 10, is conveyed by a liquid supply pump 12 of the disc centrifuge 17, and is injected into the disc centrifuge 17 from a liquid inlet 15 of the disc centrifuge 17 after the liquid flow is controlled to be stable by a frequency converter, a flowmeter 13 and an electric regulating valve 14 of the liquid supply pump 12. 110 discs 27 are arranged in the disc centrifuge 17, pretreated solution enters the drum part from the feed inlet 15, and is separated by a group of disc bundles under the action of strong centrifugal force, and lighter liquid (light phase-uranyl nitrate solution) is discharged from the liquid outlet 16 along the disc wall by taking the central hole of the disc as an interface; wherein heavy slag (impurities, silica gel, etc.) accumulates in the slag zone and is discharged from the slag outlet 28. After centrifugal separation by the disk centrifuge 17, clear liquid is discharged from the liquid outlet 16 of the disk centrifuge 17, and waste residue is discharged from the residue outlet 28 of the disk centrifuge 17, and discharged into the second residue tank 19 for temporary storage by the outer ring valve type automatic residue discharge device 18. In the operation process of the disk centrifuge 17, sealing water, slag discharge water and flushing water need to be introduced discontinuously to maintain normal operation; deionized water in the operation water tank 22 is delivered by the operation water pump 23, and enters the disc centrifuge through the sealing water electromagnetic valve 24, the washing water electromagnetic valve 25 and the deslagging water electromagnetic valve 26 according to a certain program design.
A liquid inlet sight glass 31 and a liquid outlet sight glass 32 are respectively arranged at the liquid inlet and the liquid outlet of the disc centrifuge 17, so that the liquid conditions before and after separation can be observed visually; in addition, a pressure gauge 33 and a manual pressure regulating valve 44 are arranged on the liquid outlet pipe of the disc centrifuge 17, and the separation effect can be regulated through the manual pressure regulating valve 44.
According to the method, the triuranium octoxide solution is pretreated to remove large particles with the particle size larger than 200 microns, and then a disc centrifuge is used for centrifugal separation to remove small particles with the particle size of 10-200 microns, so that insoluble solids in the triuranium octoxide solution are effectively removed, the problems of scaling and blockage of rear-end equipment through which the solution flows are greatly reduced, the surface dirt of baffle plate strings in an extraction column is reduced, the blockage risk of reboiler tube arrays is reduced, and the adaptability of a uranium purification production line to natural triuranium octoxide raw materials with different properties is improved.
Finally, it should be noted that: the above embodiments are only used to illustrate the technical solution of the present invention, and not to limit the same; while the invention has been described in detail and with reference to the foregoing embodiments, it will be understood by those skilled in the art that: the technical solutions described in the foregoing embodiments may still be modified, or some or all of the technical features may be equivalently replaced; and these modifications or substitutions do not depart from the spirit of the corresponding technical solutions of the embodiments of the present invention.
Claims (10)
1. The utility model provides a system for indissolvable solid in separation triuranium octoxide solution, a serial communication port, including pretreatment systems and centrifugation system, pretreatment systems includes the filter, the centrifugation system includes disk centrifuge, filter and disk centrifuge have the inlet respectively, liquid outlet and slag notch, coarse strainer and fine filter screen are installed in proper order in the inside of filter, the inlet and the liquid outlet of filter are located coarse strainer and fine filter screen position respectively, disk centrifuge has the rotary drum part, at rotary drum part internally mounted with a plurality of discs, disk centrifuge's inlet sets up on the rotary drum part, the liquid outlet of filter and disk centrifuge's inlet intercommunication.
2. The system of claim 1, wherein the filter has a filtration precision of 200 μ ι η; the filter is a self-cleaning filter provided with a cleaning part for cleaning a coarse filter screen and a fine filter screen.
3. The system of claim 1, wherein the pretreatment system further comprises a stock solution tank for storing the triuranium octoxide dissolving solution, the stock solution tank is communicated with the liquid inlet of the filter through a liquid inlet pipe, and a liquid supply pump, a flow meter and an electric control valve are arranged on the liquid inlet pipe.
4. The system of claim 1, wherein the pre-treatment system further comprises a first slag chute for storing filter residue of the filter, wherein a residue outlet of the filter is communicated with the first slag chute through a residue outlet pipe, and a residue outlet solenoid valve is arranged on the residue outlet pipe.
5. The system of claim 1, wherein the pretreatment system further comprises a transfer liquid tank disposed between the filter and the disk centrifuge, the transfer liquid tank having a liquid inlet, a liquid outlet and an air outlet, the liquid inlet of the transfer liquid tank being communicated with the liquid outlet of the filter, the liquid outlet of the transfer liquid tank being communicated with the liquid inlet of the disk centrifuge via a liquid inlet pipe, and a liquid supply pump, a flow meter and an electric control valve being disposed on the liquid inlet pipe.
6. The system of claim 1, wherein the centrifugal separation system further comprises an operation water tank, a sealing water inlet, a washing water inlet and a slag discharge water inlet are provided on the disk centrifuge, the operation water tank is communicated with the sealing water inlet, the washing water inlet and the slag discharge water inlet through a main water outlet pipe and three water distribution pipes, respectively, an operation water pump is provided on the main water outlet pipe, and electromagnetic valves are provided on the three water distribution pipes, respectively.
7. The system of claim 1, wherein the centrifugal separation system further comprises a second slag chute for storing filter residue of the disk centrifuge, the second slag chute being connected to a slag outlet of the disk centrifuge via an outer ring valve type automatic slag discharge device.
8. The system of claim 1, wherein a liquid inlet and a liquid outlet of the disk centrifuge are respectively provided with a sight glass; a pressure meter and a manual pressure regulating valve are arranged on the liquid outlet pipe of the disk centrifuge.
9. A process for separating a poorly soluble solid from a uranium octoxide solution, the process being carried out using the system of any one of claims 1 to 8.
10. The method of claim 9, comprising the steps of:
s1: pretreating the triuranium octoxide dissolved solution by using a pretreatment system to remove large-particle substances with the particle size of more than 200 mu m to obtain a pretreatment solution;
s2: and (3) carrying out centrifugal separation on the pretreatment liquid by adopting a centrifugal separation system to remove small particles with the particle size of 10-200 mu m.
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CN202822946U (en) * | 2012-09-04 | 2013-03-27 | 清华大学 | Filtering device |
CN105413892A (en) * | 2015-12-15 | 2016-03-23 | 宜兴市华鼎粮食机械有限公司 | Disc-type centrifuge rotary drum with wear-resistant lining |
CN216418610U (en) * | 2021-10-20 | 2022-05-03 | 河南永威复合新材料有限公司 | Novel pretreatment of wood-based plate material sewage device |
CN114887389A (en) * | 2022-06-24 | 2022-08-12 | 北京博大新元房地产开发有限公司 | Multistage preprocessing device of sewage that construction engineering used |
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2022
- 2022-10-17 CN CN202211268611.5A patent/CN115487602A/en active Pending
Patent Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
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CN202822946U (en) * | 2012-09-04 | 2013-03-27 | 清华大学 | Filtering device |
CN105413892A (en) * | 2015-12-15 | 2016-03-23 | 宜兴市华鼎粮食机械有限公司 | Disc-type centrifuge rotary drum with wear-resistant lining |
CN216418610U (en) * | 2021-10-20 | 2022-05-03 | 河南永威复合新材料有限公司 | Novel pretreatment of wood-based plate material sewage device |
CN114887389A (en) * | 2022-06-24 | 2022-08-12 | 北京博大新元房地产开发有限公司 | Multistage preprocessing device of sewage that construction engineering used |
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