An automatic extraction device and method of uranium nuclides

Abstract

The application discloses a kind of uranium nuclide automatic extraction device and method, wherein, device includes dissolving target device, acid regulator, extractor, purifier, waste liquid tank, product tank, control system and shielding box, dissolving target device, acid regulator, extractor, purifier, waste liquid tank, product tank are connected by conveying pipe and valve, liquid conveying power is provided by peristaltic pump, control system is set in shielding box, and relevant components in shielding box are electrically connected.The application also describes a method for extracting a uranium nuclide solution substantially free of impurities from an irradiated thorium target material.The uranium nuclide automatic extraction device of the present application can achieve rapid and efficient extraction and purification of uranium nuclides from irradiated thorium target material.The device has the characteristics of simple structure, compactness and automation operation, which greatly improves the production efficiency and reduces the radiation dose received by the operator.

Description

TECHNICAL FIELD

[0001] The present application belongs to the technical field of radionuclide preparation, and particularly relates to a device and method for extracting a uranium nuclide solution substantially free of impurities from an irradiated thorium target material. BACKGROUND

[0002] Uranium isotopes have various uses in the nuclear industry. For example, uranium-233 is irreplaceable as a diluent standard substance in the precise and accurate measurement of uranium in the fields of nuclear fuel cycle reprocessing, radiochemical analysis, etc. At the same time, uranium-233 is a key core material of thorium-based molten salt reactors and has been widely used in the development of new nuclear energy. In addition, uranium-233 can also be used as a generator raw material for the preparation of the important medical nuclide actinium-225.

[0003] Studies have shown that uranium-233 is mainly generated by irradiating thorium-232 target material with reactor thermal neutrons. During the process of generating uranium-233 from the irradiated thorium-232 target material, a large amount of fission product elements are also produced, so the chemical composition of the irradiated Th-232 target material is complex. Therefore, it is necessary to extract and separate the uranium-233 nuclide product from the irradiated thorium-232 target material. Typically, the irradiated thorium target material needs to be dissolved and chemically separated to extract and separate the uranium nuclide substantially free of impurities from the irradiated target material with numerous nuclides.

[0004] Some documents currently disclose separation methods for extracting uranium nuclides from irradiated thorium-232 target material, such as the Thorex process and the Interim-23 process. The irradiated thorium-232 target material has a very high radioactivity, and it is very important to reduce the exposure of operators to radiation during the extraction of uranium nuclides. Therefore, the uranium nuclide extraction system should be placed in a shielded chamber. However, there is no report on an automatic extraction device for uranium nuclides at home and abroad. SUMMARY

[0005] The technical problem to be solved by the present application is to provide a simple, efficient and automatic extraction device and method for uranium nuclides in a complex matrix of irradiated thorium target material.

[0006] The present application is suitable for a uranium nuclide automatic extraction device, characterized in that the uranium nuclide automatic extraction device comprises a target dissolving device, an acid adjusting device, an extractor, a purifier, a waste liquid tank, a product tank, a control system and a shielded chamber, the target dissolving device, the acid adjusting device, the extractor, the purifier, the waste liquid tank and the product tank are connected through liquid conveying pipes and valves, and the liquid conveying power is provided by a peristaltic pump.

[0007] The target dissolving device comprises a dissolving bottle, a condenser, a suction pump, and an absorption bottle arranged in sequence, the dissolving bottle has at least two ports, the first port is connected with the condenser, and the second port is connected with an acid adjuster through a conveying pipe; the lower end of the condenser is connected with the dissolving bottle, and the upper end is connected with the suction pump through a conveying pipe; the suction pump has two ports, the first port is connected with the condenser through a conveying pipe, and the second port is connected with the absorption bottle through a conveying pipe; the absorption bottle has two ports, the first port is connected with the suction pump through a conveying pipe, and the second port is communicated with the atmosphere; the dissolving bottle is placed on a magnetic stirring heater;

[0008] The acid adjuster comprises an acid adjuster bottle, an electromagnetic stirrer, and a non-contact liquid level sensor; the acid adjuster bottle has two ports, the first port is connected with the dissolving bottle through a conveying pipe, and the second port is connected with a first transfer bottle through a conveying pipe; the non-contact liquid level sensor detects the liquid volume in the acid adjuster bottle through optical signals.

[0009] The extractor comprises the first transfer bottle and a separation column; the first transfer bottle has two ports, the first port is connected with the acid adjuster bottle through a conveying pipe, and the second port is connected with a liquid inlet at the lower end of the separation column through a conveying pipe; a liquid outlet at the upper end of the separation column is connected with a waste liquid tank and a second transfer bottle through an electromagnetic multi-way valve and a conveying pipe.

[0010] The purifier comprises the second transfer bottle and a purification column; the second transfer bottle has two ports, the first port is connected with the separation column through a conveying pipe, and the second port is connected with a liquid inlet at the lower end of the purification column through a conveying pipe; a liquid outlet at the upper end of the purification column is connected with the waste liquid tank and a product tank through an electromagnetic multi-way valve and a conveying pipe.

[0011] Further, a radiation shielding box encloses the target dissolving device, the acid adjuster, the extractor, the purifier, the waste liquid tank, and the product tank.

[0012] Further, a control system is arranged outside the radiation shielding box and is electrically connected with the components in the radiation shielding box; the electromagnetic stirring heater, the non-contact liquid level sensor, the peristaltic pump, and the electromagnetic valve switch are controlled by the control system to realize remote control and automatic operation of the device, and preferably, the control system is a microprocessor capable of executing instructions.

[0013] Further, the separation column is a cation resin exchange column, and the purification column is an anion resin exchange column; the material of the connecting pipes is polytetrafluoroethylene, and the materials of the dissolving bottle, the condenser, the absorption bottle, the separation column, the purification column, the transfer bottles, the waste liquid tank, and the product tank are quartz glass.

[0014] In addition, the present application provides a method for extracting uranium nuclides from irradiated thorium target material by using the uranium nuclide automatic extraction device.

[0015] The irradiated thorium target material is transferred to a dissolving bottle;

[0016] The dissolving solution is transferred to the dissolving bottle by controlling the system to start the peristaltic pump and the on-off electromagnetic valve according to the programmed instructions, and the thorium target material is dissolved by heating the magnetic stirrer. The exhaust gas in the dissolving process is directed to flow by the air pump and is absorbed by the absorption bottle.

[0017] After the thorium target material is completely dissolved, the dissolving solution is transferred to the acid adjuster by the peristaltic pump for volume calibration and acidity adjustment.

[0018] The dissolving solution after the acidity adjustment is transferred to the separation column by the peristaltic pump, the uranium nuclide is adsorbed on the anion exchange resin in the separation column, the impurity nuclide flows out with the solution, the impurity nuclide remaining on the separation column is eluted by the washing solution, and the uranium nuclide is eluted from the separation column.

[0019] The eluted uranium nuclide is washed out from the purification column to form a solution of the uranium nuclide without impurities.

[0020] Further, the dissolving solution in the dissolving bottle is concentrated hydrochloric acid.

[0021] Further, the dissolving bottle is placed on the heating magnetic stirrer, the irradiated target material is accelerated to dissolve by the heating and stirring, and the concentration of the dissolving solution is uniform.

[0022] Further, the separation column is filled with strong acid type anion exchange resin, 10 column volumes of washing solution are used for washing, and 15 column volumes of elution solution are used for eluting the uranium nuclide.

[0023] Further, the purification column is filled with strong acid type cation exchange resin, and 20 column volumes of elution solution are used for eluting the uranium nuclide.

[0024] The device and method of the present application relate to a solution of uranium nuclide substantially without impurities extracted from the irradiated thorium target material. By using the carefully designed system and method, about 10000 to 10000000 or more impurities can be removed. The device has the characteristics of simple structure, compactness and automatic operation, which greatly improves the production efficiency and reduces the radiation dose of the operator. BRIEF DESCRIPTION OF DRAWINGS

[0025] Figure 1 is the overall layout and pipe connection schematic diagram of the uranium nuclide automatic extraction device of the present application;

[0026] Figure 2 is the method flow chart of extracting the uranium nuclide of the present application; DETAILED DESCRIPTION

[0027] The present application will be further described below in combination with the drawings and specific embodiments.

[0028] Embodiment one

[0029] The device and method of the present application relate to a method for extracting a uranium isotope solution substantially free of impurities from an irradiated thorium target. Figure 1 The device includes a target dissolving device, an acid adjusting device, an extractor, a purifier, a waste liquid tank, a product tank, a control system and a shielding box. The target dissolving device, the acid adjusting device, the extractor, the purifier, the waste liquid tank and the product tank are connected by liquid delivery pipes and valves, and the liquid delivery power is provided by a peristaltic pump.

[0030] The target dissolving device includes a dissolving bottle 1, a condenser tube 2, an air pump II and an absorption bottle 3 arranged in sequence. The dissolving bottle 1 is a round-bottom bottle with three necks. One neck is sealed by a ring-shaped rubber gasket plug 11 to realize feeding of the irradiated sample. One neck 12 is connected with the bottom of the condenser tube 2. The other neck is inserted into a liquid delivery pipe 13 to realize liquid delivery and connection with the acid adjusting device. The top of the condenser tube 2 is connected with one end of the air pump II through a one-way valve III. The other end of the air pump II is connected with one end of the absorption bottle 3 through a delivery pipe. The other end of the absorption bottle 3 is connected with the atmosphere. The absorption bottle 3 is filled with a strong alkaline solution to absorb the acidic waste generated in the dissolving process, so as to prevent the dissolving solution from being directly volatilized into the environment during the dissolving process of the irradiated sample. The dissolving bottle 1 is placed on a magnetic stirring heater 4 to realize rapid dissolving of the irradiated sample through heating and stirring, and to ensure uniformity of the concentration of the dissolving solution. The magnetic stirring heater 4 is fixedly arranged on a lifting table 5 to realize lifting of the position. When heating, the lifting table 5 is lifted to make the heater 4 closely contact with the dissolving bottle 1 to heat the dissolving solution. After the dissolving is completed, the lifting table 5 is lowered to separate the heater 4 from the dissolving bottle 1 to rapidly cool the dissolving solution. The dissolving bottle 1, the condenser tube 2 and the absorption bottle 3 are made of quartz glass, and the feeding plug is made of polytetrafluoroethylene.

[0031] The acid adjusting device mainly includes an acid adjusting bottle 6, an electromagnetic stirrer 7 and a non-contact liquid level sensor 8. The top of the acid adjusting bottle 6 is inserted into three liquid delivery pipes. One pipe 61 is connected with the liquid delivery pipe 13 of the dissolving bottle. One pipe 62 is connected with a reagent delivery pipe. The other pipe 63 is connected with a transfer bottle 9. The non-contact liquid level sensor 8 detects the volume of the liquid in the acid adjusting bottle through optical signals.

[0032] The extractor includes a first transfer bottle 9 and a separation column 10. The top of the first transfer bottle 9 is inserted into three liquid delivery pipes. One pipe 91 is connected with the liquid delivery pipe 63 of the acid adjusting bottle 6. One pipe 92 is connected with a reagent delivery pipe. The other pipe 93 is connected with the bottom of the separation column 10. The separation column 10 is an anion resin column. The top of the separation column 10 is connected with a waste liquid tank 13 and a transfer bottle 11 through a liquid delivery pipe.

[0033] The purifier comprises a second transfer bottle 11 and a purification column 12. The top of the second transfer bottle 11 is provided with three liquid delivery tubes, one 111 of which is connected with the separation column 10, one 112 is connected with the reagent delivery tube, and the other 113 is connected with the bottom of the purification column 12. The purification column 12 is a cation resin column. The top of the purification column 12 is connected with the waste liquid tank 13 and the product tank 14 through liquid delivery tubes.

[0034] The valve comprises six electromagnetic valves. The six inlets 111, 112, 113, 114, 115 and 116 of the six-way valve I are respectively connected with the dissolving liquid, hydrochloric acid, washing liquid 1, elution liquid 1, washing liquid 2 and elution liquid 2, and the outlet 117 is connected with the peristaltic pump I. The six-way valve II comprises at least five ports, wherein the inlet 221 is connected with the peristaltic pump I, the outlets 222, 223 and 224 are respectively connected with the liquid delivery tube 13 in the dissolving bottle 1, the liquid delivery tube 62 in the acid adjusting bottle 6 and the three-way valve IV. One end of the one-way valve III is connected with the top of the condenser tube 2, and the other end is connected with the air pump II. One end 441 of the three-way valve IV is connected with the outlet 224 of the six-way valve II, one end 442 is connected with the liquid delivery tube 92 in the transfer bottle 9, and the other end 443 is connected with the liquid delivery tube 112 in the transfer bottle 11. One end 551 of the three-way valve V is connected with the top of the separation column 10, one end 552 is connected with the waste liquid tank 13, and the other end 553 is connected with the liquid delivery tube 111 in the transfer bottle 11. One end 661 of the three-way valve VI is connected with the top of the purification column 12, one end 662 is connected with the waste liquid tank 13, and the other end 663 is connected with the product tank 14.

[0035] The peristaltic pump comprises six peristaltic pumps. One end of the peristaltic pump I is connected with the six-way valve I, and the other end is connected with the six-way valve II. One end of the air pump II is connected with the one-way valve, and the other end is connected with the absorption bottle 3. One end of the peristaltic pump III is connected with the liquid delivery tube 13 in the dissolving bottle 1, and the other end is connected with the liquid delivery tube 61 in the acid adjusting bottle 6. One end of the peristaltic pump IV is connected with the liquid delivery tube 63 in the acid adjusting bottle 6, and the other end is connected with the liquid delivery tube 91 in the transfer bottle 9. One end of the peristaltic pump V is connected with the liquid delivery tube 93 in the transfer bottle 9, and the other end is connected with the bottom of the separation column 10. One end of the peristaltic pump VI is connected with the liquid delivery tube 113 in the transfer bottle 11, and the other end is connected with the bottom of the purification column 12.

[0036] The radiation shielding box 15 encloses the dissolving device, the acid adjusting device, the extraction device, the purifier, the waste liquid tank, the product tank, part of the pump system and the valve system. The six-way valve I and the peristaltic pump I are arranged outside the radiation shielding box 15.

[0037] The control system 16 is arranged outside the radiation shielding box 15 and is electrically connected with the components in the radiation shielding box 15; the electromagnetic stirring heaters 5 and 7, the non-contact liquid level sensor 8, the pump system, the electromagnetic valve switch and the like are controlled by the control system 16 to realize remote control and automatic operation of the device, and preferably, the control system 16 is a microprocessor capable of executing instructions.

[0038] The method for automatically extracting uranium nuclides by using the device is as follows:

[0039] 1) The irradiated thorium target is put into the dissolving bottle 1 through the feeding opening of the sealing plug 11, the sealing plug 11 is covered, the control system is started, the six-way valve I and the six-way valve II 22 connected with the dissolving solution are sequentially opened, the dissolving solution is quantitatively pumped into the dissolving bottle 1 by the peristaltic pump I through the liquid delivery pipe 13 of the dissolving bottle 1, after the pumping is completed, the six-way valve I, the six-way valve II 22 and the peristaltic pump I are closed.

[0040] 2) The electromagnetic stirring heater 4 is lifted to the bottom of the dissolving bottle 1 by using the lifting platform 5, then the stirring and heating are started; the waste gas generated in the heating and dissolving process is condensed by the condenser 2, then is pumped into the absorption bottle 3 for purification treatment by the one-way valve III and the air pump II; after the target material is completely dissolved, the electromagnetic stirring heater 4 is turned off and the lifting platform 5 is reset, and the dissolving solution is cooled to room temperature.

[0041] 3) The peristaltic pump III is started, the dissolving solution is transferred to the acid adjusting bottle 6 through the liquid delivery pipe 13 of the dissolving bottle 1; the six-way valve I 12 and the six-way valve II 23 connected with the hydrochloric acid are sequentially opened after the dissolving solution is accurately measured by using the non-contact liquid level sensor 8, the hydrochloric acid is quantitatively pumped into the acid adjusting bottle 6 by the peristaltic pump I through the liquid delivery pipe 62 of the acid adjusting bottle 6, after the pumping is completed, the six-way valve I, the six-way valve II and the peristaltic pump I are closed, and the electromagnetic stirrer 7 is started to stir the dissolving solution in the acid adjusting bottle 6 uniformly.

[0042] 4) The dissolving solution after the acidity is adjusted is transferred to the transfer bottle 9 by using the peristaltic pump IV through the liquid delivery pipe 63 of the acid adjusting bottle 6; then the dissolving solution is pumped into the separation column 10 by using the peristaltic pump V through the liquid delivery pipe 93 of the transfer bottle 9; the uranium nuclides are captured by the anion exchange resin in the separation column, at the same time, the thorium and other fissile product nuclides pass through the separation column, enter the waste liquid tank 13 through the three-way valve V.

[0043] 5) The six-way valve I port 13 and the six-way valve II port 24 connected with the washing liquid 1 are opened, the washing liquid 1 is quantitatively pumped into the transfer bottle 9 by using the peristaltic pump I through the liquid delivery pipe 92 of the transfer bottle 9, after the pumping is completed, the six-way valve I, the six-way valve II and the peristaltic pump I are closed; the transfer bottle 9 is washed with the washing liquid 1, then the washing liquid 1 is pumped into the separation column 10 by using the peristaltic pump V through the liquid delivery pipe 93 of the transfer bottle 9; any residual thorium and other impurities are washed out of the anion resin and enter the waste liquid tank 13 through the three-way valve V.

[0044] 6) Open the six-way valve I port 14 and six-way valve II port 24 connected with eluent 1, use peristaltic pump I to pump the eluent 1 through the liquid transfer tube 92 of the transfer bottle 9, after the pumping is completed, close the six-way valve I, six-way valve II and peristaltic pump I; use the eluent 1 to wash the transfer bottle 9, then use peristaltic pump V to pump the eluent 1 through the liquid transfer tube 93 of the transfer bottle 9 into the separation column 10; all the uranium nuclides are eluted from the anion exchange resin and pumped into the transfer bottle 11 through the liquid transfer tube 111 of the transfer bottle 11 via the three-way valve V port 52.

[0045] 7) Use peristaltic pump VI to pump the uranium nuclide solution through the liquid transfer tube 113 of the transfer bottle 11 into the purification column 12; the uranium nuclides, residual thorium and other impurity nuclides are captured by the cation exchange resin in the purification column 12; the waste liquid after column is introduced into the waste liquid tank 13 via the three-way valve VI port 61;

[0046] 8) Open the six-way valve I port 15 and six-way valve II port 24 connected with washing solution 2, use peristaltic pump I to pump the washing solution 2 through the liquid transfer tube 112 of the transfer bottle 11, after the pumping is completed, close the six-way valve I, six-way valve II and peristaltic pump I; use the washing solution 2 to wash the transfer bottle 11, then use peristaltic pump VI to pump the washing solution 2 through the liquid transfer tube 113 of the transfer bottle 11 into the separation column 12; the waste liquid after column is introduced into the waste liquid tank 13 via the three-way valve VI port 61;

[0047] 9) Open the six-way valve I port 16 and six-way valve II port 24 connected with eluent 2, use peristaltic pump I to pump the eluent 2 through the liquid transfer tube 112 of the transfer bottle 11, after the pumping is completed, close the six-way valve I, six-way valve II and peristaltic pump I; pump the eluent 2 through the liquid transfer tube 113 of the transfer bottle 11 into the separation column 12; all the U-233 nuclides are eluted from the cation exchange resin and introduced into the product tank 14 via the three-way valve VI port 62.

[0048] Thus the irradiated thorium target is dissolved and the uranium nuclides are extracted and purified. The whole process can be completed within 4 hours, which greatly shortens the separation time and reduces the radiation dose of the operator.

[0049] The above embodiment is only an example of the system and method of the present application. There are several design variations of the system and method of the present application, according to different separation systems, a conditioning tank, different levels of purifiers, washing solution and eluent solution can be introduced into the system to separate different radioactive nuclide products from the irradiated target sample. For example, the present application can be used to extract plutonium nuclides from the irradiated uranium target sample, extract plutonium nuclides from the irradiated neptunium target, or extract americium from the plutonium raw material, etc., to provide standard materials for radiochemical analysis test. The device of the present application can also be used to purify thorium-229 and actinium-225, which can be used for radiotherapy.

[0050] Various modifications can be made in accordance with the desired feedstock and products to be separated without departing from the true spirit and scope of the inventive concept. The application is not limited to the specific embodiments described above, since variations can be made in the details of the construction and arrangement of parts without departing from the scope of the application, which is defined in the claims.

Claims

1. An automated extraction device for uranium species, characterized by: The automatic uranium extraction device comprises a target dissolving device, an acid adjusting device, an extractor, a purifier, a waste liquid tank (13), a product tank (14), a control system and a shielding box, the target dissolving device, the acid adjusting device, the extractor, the purifier, the waste liquid tank (13) and the product tank (14) are connected through liquid conveying pipes and valves, and the liquid conveying power is provided by a peristaltic pump I; The target dissolving device comprises a dissolving bottle (1), a condenser (2), a suction pump II and an absorption bottle (3) arranged in sequence, the dissolving bottle (1) has at least two ports, a first port is connected with the condenser (2), and a second port is connected with the acid adjusting device through a conveying pipe; the lower end of the condenser (2) is connected with the dissolving bottle (1), and the upper end is connected with the suction pump II through a conveying pipe; the suction pump II has two ports, a first port is connected with the condenser (2) through a conveying pipe, and a second port is connected with the absorption bottle (3) through a conveying pipe; the absorption bottle (3) has two ports, a first port is connected with the suction pump II through a conveying pipe, and a second port is communicated with the atmosphere; the dissolving bottle (1) is placed on a magnetic stirring heater (4); The acid adjusting device comprises an acid adjusting bottle (6), an electromagnetic stirrer (7) and a non-contact liquid level sensor (8); the acid adjusting bottle (6) has two ports, a first port is connected with the dissolving bottle (1) through a conveying pipe, and a second port is connected with a first transfer bottle (9) through a conveying pipe; the non-contact liquid level sensor (8) detects the liquid volume in the acid adjusting bottle (6) through optical signals; the extractor comprises the first transfer bottle (9) and a separation column (10); the first transfer bottle (9) has two ports, a first port is connected with the acid adjusting bottle (6) through a conveying pipe, and a second port is connected with a liquid inlet at the lower end of the separation column (10) through a conveying pipe; a liquid outlet at the upper end of the separation column (10) is connected with the waste liquid tank (13) and a second transfer bottle (11) through a conveying pipe and an electromagnetic multi-way valve; The purifier comprises the second transfer bottle (11) and a purification column (12); the second transfer bottle (11) has two ports, a first port is connected with the separation column (10) through a conveying pipe, and a second port is connected with a liquid inlet at the lower end of the purification column (12) through a conveying pipe; a liquid outlet at the upper end of the purification column (12) is connected with the waste liquid tank (13) and the product tank (14) through a conveying pipe and an electromagnetic multi-way valve.

2. The apparatus of claim 1, wherein: The radiation shielding box encloses the target dissolving device, the acid adjusting device, the extractor, the purifier, the waste liquid tank (13) and the product tank (14).

3. The device according to claim 1, characterized in that: The control system is arranged outside the radiation shielding box and is electrically connected with the components in the radiation shielding box; the electromagnetic stirring heater (4), the non-contact liquid level sensor (8), the peristaltic pump I and the electromagnetic valve switch are controlled through the control system, so that remote control and automatic operation of the device are realized.

4. The device according to claim 3, characterized in that: The control system is a microprocessor capable of executing instructions.

5. The apparatus of claim 1, wherein: The separation column (10) is a cation resin exchange column, and the purification column (12) is an anion resin exchange column; the material of the connecting pipes is polytetrafluoroethylene, and the materials of the dissolving bottle (1), the condenser (2), the absorption bottle (3), the separation column (10), the purification column (12), the transfer bottles, the waste liquid tank (13) and the product tank (14) are quartz glass.

6. A method for extracting uranium nuclides from irradiated thorium target material using the automatic uranium nuclide extraction device of claim 1, comprising the steps of: transferring the irradiated thorium target material into the dissolving bottle (1); transferring the dissolving solution into the dissolving bottle (1) by sequentially starting the peristaltic pump I and the on-off electromagnetic valve according to the programmed instructions by the control system, dissolving the thorium target material by heating with the magnetic stirrer, and realizing directional flow of tail gas during the dissolving process by the air pump II and absorbing the tail gas by the absorption bottle (3); after the thorium target material is completely dissolved, transferring the dissolving solution into the acid adjuster by the peristaltic pump I for volume calibration and acidity adjustment; transferring the dissolving solution after the acidity adjustment into the separation column (10) by the peristaltic pump I, adsorbing the uranium nuclides on the anion exchange resin in the separation column (10), flowing the impurity nuclides with the solution, eluting the impurity nuclides remaining on the separation column (10) by the washing solution, and eluting the uranium nuclides from the separation column (10); eluting the eluted uranium nuclides through the purification column (12), eluting the uranium nuclides from the purification column (12), and forming the solution of the uranium nuclides without impurities.

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