CN211864500U - Extraction from dissolved irradiated uranium target tail gas131I apparatus - Google Patents
Extraction from dissolved irradiated uranium target tail gas131I apparatus Download PDFInfo
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- CN211864500U CN211864500U CN202020023744.6U CN202020023744U CN211864500U CN 211864500 U CN211864500 U CN 211864500U CN 202020023744 U CN202020023744 U CN 202020023744U CN 211864500 U CN211864500 U CN 211864500U
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Abstract
The disclosure belongs to the field of radionuclide preparation, and particularly relates to extraction from dissolved irradiated uranium target tail gas131I, the apparatus comprising: the device comprises a gas blowing cylinder, an acid feeding liquid tank, a dissolver, a liquid absorption column, an elution liquid tank, an anion exchange resin column, a distiller heater, a product bottle, a purification column and a gas storage tank; thereby forming a set of complete dissolved irradiated uranium target tail gas for extracting radionuclide131I recovery device, reducing the irradiation of dissolutionIn tail gas of uranium targets131I content, thereby reducing the proportion of harmful substances in the tail gas of the dissolved irradiation uranium target, effectively reducing environmental pollution and recycling131I has a certain economic value, thereby reducing131And I, the production cost.
Description
Technical Field
The disclosure belongs to the field of radionuclide preparation, and particularly relates to extraction from dissolved irradiated uranium target tail gas131I.
Background
99mTc drugs are the most widely used radiodiagnostic drugs in modern nuclear medicine, and the nuclides are generally artificial radionuclides99The Mo is obtained by the decay of the Mo,99the half life of Mo is 66 h. At present, the world99The main source of Mo is generated by uranium-235 fission reaction through reactor irradiation99Mo, uranium target (235U) is subjected to fission reaction under the action of thermal neutrons after being stacked,235the U reaction cross-section is 586 b. Generating99The Mo fission reaction equation is:
235U(nf)236U→99Mo+134Sn+3n
at present, fission is produced on a large scale99Mo is extracted and purified from fission products through a complicated recovery process99Mo to obtain high purity medical use99Mo。
235U is subjected to fission reaction under the action of thermal neutrons to generate99While Mo (amount of only 6.1 mass% of fission products), hundreds of other radioactive fission products are produced, including radioactive iodine (I)129I、131I、132I、133I、135I) And the like. The generation of radioactive iodine is mainly as follows131The content of the fission product I is 2.84% (half-life period is 8.02 days, irradiation energy is 806.9keV, beta)-A ray),133the content of I is 6.77% (half-life period is 20.8 hours, irradiation energy is 1538keV, beta)-A ray). Producing other radioiodines with very little content, short half-life, longest length132I is only 2.26 hours.
235U(nf)236U→131I+101Y+4n
235U(nf)236U→133I+100Y+3n
In that235Radioactive iodine produced by U fission exists in the target in the form of solid solution235In the crystal lattice of U, iodine substance is easy to sublimate and volatilize under normal temperature and pressure, and along with the dissolution process of the target after irradiation, the iodine substance is cracked with other substancesThe gas is changed into tail gas to be released.
131The content of I is 2.84% (half-life period is 8.02 days, irradiation energy is 806.9KeV, beta)-A ray),133the content of I is 6.77% (half-life period 20.8 hours, irradiation energy 1538KeV, beta)-A ray).
131I may be bombarded with slow neutrons by the reactor130Te or bombardment with deuterium in cyclotrons130Te and other methods.131The emitted beta rays can be used for treating thyroid diseases, and the emitted gamma rays can be used for imaging and diagnosing organs such as thyroid, liver, lung and the like, and can also be used for measuring the functions of organs such as kidney, thyroid and the like. The method can be industrially used for measuring the water absorption capacity and the change of each oil layer of the water injection well of the oil field so as to distribute water flow in time and keep the high and stable yield of the oil field.
Therefore, while dissolving the target after irradiation, collecting the iodine-131 generated in the process, the radionuclide with various requirements can be obtained131And I, the radioactive tail gas purification treatment process can be reduced, so that the discharged gas reaches the environmental protection standard.
SUMMERY OF THE UTILITY MODEL
Objects of the invention
In order to overcome the deficiencies of the prior art, the present disclosure provides a method capable of extracting from dissolved irradiated uranium target tail gas131I.
(II) technical scheme
Extraction from dissolved irradiated uranium target tail gas131I, the apparatus comprising: a gas blowing cylinder, an acid feeding liquid tank, a dissolver, a liquid absorption column, an elution liquid tank, an anion exchange resin column, a distiller heater, a product bottle, a purification column, a gas storage tank and the like.
Wherein, the air blowing bottle is respectively connected with the acid feeding liquid tank and the dissolver through pipelines; the acid feeding liquid tank is connected with the dissolver through a pipeline; a feeding pipeline is arranged on the acid feeding liquid tank, and a valve is arranged on the feeding pipeline; the dissolver is connected with the liquid absorption column through a pipeline; the liquid absorption column is respectively connected with the anion exchange resin column, the gas storage tank and the purification column through pipelines; the anion exchange resin column is connected with the distiller through a pipeline; the elution material liquid tank is connected with the anion exchange resin column through a pipeline, a feeding pipeline is arranged at the top of the elution material liquid tank, and a valve is arranged on the pipeline; a distiller heater is arranged at the bottom of the distiller; the distiller is connected with the purification column through a pipeline; the purification column is respectively connected with the product bottle and the gas storage tank through pipelines; the air storage tank is provided with an exhaust pipeline, and the product bottle is positioned in the cold trap.
The gas-blowing cylinder is filled with high-purity gas which is 99% of inert gas.
The connecting pipeline of the gas drum and the dissolver extends into the bottom of the dissolver.
The bottom of the liquid absorption column is provided with a sieve plate, and alkaline liquid is arranged in the liquid absorption column.
The eluent is filled in the eluent tank, and the eluent is alkaline liquid.
The number of the liquid absorption columns is more than or equal to 1, and when the number of the liquid absorption columns is more than 1, the liquid absorption columns are connected in series.
The bottom of the liquid absorption column is provided with an alkaline liquid outlet.
Valves are arranged on the connecting pipelines of the gas blowing cylinder, the acid feeding liquid tank and the dissolver; a valve is arranged on a connecting pipeline of the acid feed liquid tank and the dissolver; a valve is arranged on a connecting pipeline of the dissolver and the liquid absorption column; valves are arranged on the connecting pipelines of the liquid absorption column, the purification column and the gas storage tank; a valve for controlling the feeding speed of the elution material liquid tank is arranged on a connecting pipeline of the elution material liquid tank and the anion exchange resin column; the exhaust pipeline of the gas storage tank is provided with a valve.
Pressure gauges are arranged on the gas blowing cylinder and the gas storage cylinder.
The alkaline liquid is sodium hydroxide solution, potassium hydroxide solution or ammonia water, and the pH value is more than 10.
(III) advantageous effects
The method extracts the radionuclide from the tail gas of the complete dissolved irradiation uranium target131I recovery device reduces tail gas of dissolved and irradiated uranium target131I content, thereby reducing the proportion of harmful substances in the tail gas of the dissolved irradiation uranium target, effectively reducing environmental pollution and recycling131I has a certain economic value, thereby reducing131And I, the production cost.
Drawings
FIG. 1 shows a tail gas from dissolving irradiated uranium target of the present disclosure131I, schematic diagram of the apparatus;
FIG. 2 is a schematic view of connection in the case of multiple stages of the liquid absorption column of FIG. 1;
FIG. 3 is a schematic view of the structure of the liquid absorption column in FIG. 1;
figure 4 is a schematic view of the screen deck structure of figure 3;
FIG. 5 is a schematic diagram of the anion exchange resin structure of FIG. 1;
FIG. 6 is a schematic diagram of the distiller of FIG. 1;
FIG. 7 is a schematic diagram of the purification column of FIG. 1;
FIG. 8 is a schematic view of the acid feed tank configuration of FIG. 1;
FIG. 9 is a schematic diagram of the eluent tank configuration of FIG. 1;
wherein 1, a gas drum; 2, a dissolver; 3 a liquid absorption column; 4 anion exchange resin column; 5, a distiller; 6 a distiller heater; 7, product bottles; 8, purifying the column; 9 gas storage tank; 10. 12, 13, 14, 16, 17, 18, 20, 21, 22, 23 valves; 11. 24 pressure gauge; 15 eluting the feed liquid tank; 19 feeding the acid material liquid tank; 25 sieve plates.
Detailed Description
To better illustrate the extraction of the disclosure from dissolved uranium target tail gas131The device of the invention is described in detail with reference to the following embodiments;
fission of fuel99Production of Mo, first of all from235The target made of U is sent into a reactor to be irradiated for a certain time, taken out and transferred into a shielded hot room, and placed into an all-metal closed dissolving system to be dissolved to obtain235U target dissolving solution, treating the dissolving solution in the disclosed device, and dissolving the solution131And I, collecting and purifying.
As shown in figure 1 of the drawings, in which,131the I extraction device consists of a dissolved degassing part, a multistage absorption part and a chemical treatment part, and the main components of the I extraction device comprise an air blowing bottle 1, a dissolver 2, a liquid absorption column 3, an anion exchange resin column 4, a distiller 5, a distiller heater 6, a product bottle 7, a purification column 8, an air storage tank 9, an elution material liquid tank 15, an acid feeding liquid tank 19 and the like. The iodine-containing gas generated by acidifying the dissolved solution enters an absorption column, is absorbed by the solution and then is chemically treated to obtain the iodine-containing gas131And (I) products.
Wherein the dissolved degassing part comprises a gas blowing cylinder 1, an acid feed liquid tank 19 and a dissolver 2; the gas blowing bottle 1 is filled with inert gas with purity of more than 99 percent, the inert gas is connected into the dissolver 2 through a pipeline, the connecting pipeline extends to the bottom of the dissolver 2, gas is provided when the target piece is dissolved, the dissolved solution gas of strong acid liquid such as nitric acid or sulfuric acid is blown and stirred, the acid adding amount is controlled by a valve 20 in an acid material liquid tank 19, and after the dissolution and acidification, the dissolved gas is matched with the blowing gas131And I, expelling. More than 99% of fission iodine and radioactive gas can be expelled in the process.
Wherein the multi-stage absorption part comprises a liquid absorption column 3, and the liquid absorption column 3 is internally provided with absorption131And (I) an alkaline liquid such as sodium hydroxide or potassium hydroxide. The liquid absorption column 3 is131The core part of the I extraction device can be designed into one stage to multiple stages according to the processing capacity in the device. And after irradiation, gas discharged from the solution of the uranium target after degassing is introduced into the liquid absorption column 3.
The sieve plate 25 is additionally arranged at the bottom of the liquid absorption column 3 to break larger bubbles into fine bubbles so as to ensure that iodine and other gases generated during dissolution are better absorbed. After the saturated alkaline liquid is discharged and transferred, the liquid absorption column 3 is replaced with new alkaline liquid for the next collection.
Wherein the chemical treatment part comprises an anion exchange resin column 4, after the alkaline liquid of the liquid absorption column 3 is absorbed and saturated, the operation is carried out by a hot chamber manipulator, and a control valve at the bottom of the liquid absorption column 3 is opened to discharge and collect the saturated alkaline liquid.
The saturated alkaline liquid is transferred to a chemical treatment part in a recovery process hot chamber, and the recovered fission iodine is extracted by eluting through an anion exchange resin column 4. The eluent liquid tank 15 controls the adding speed of the eluent of the alkaline solution such as ammonia water through a valve 16, so that more than 99% of iodine is eluted and collected into the eluent.
The fission iodine solution extracted and eluted by the anion exchange resin column 4 is transferred to a distiller 5 to be heated, the fission iodine in the eluent is purified and distilled out, the purified iodine is concentrated in a purification column 8, and the iodine is subpackaged according to the specification of a required product to prepare an iodine product.
By adopting the device, all the valves are in a closed state initially, the valves 18 and 19 are opened, and acid liquor is added into the dissolver 2 to dissolve the irradiated target piece. In the dissolving process of the uranium target, the valve 23 is opened to blow gas into the dissolving solution to expel radioactive gas generated by dissolving the uranium 235, the valves 21, 17 and 12 are opened to pass the expelled gas through the liquid absorption column 3,131i are collected in the liquid absorption column 3, and the rest gas enters a gas storage tank 9 for storage.
After completion of the dissolution, the valves 21 and 17 are closed, and the liquid absorption column 3 is filled with the solvent131Transferring the absorption solution of I to an anion exchange resin column 4 for131I initial recovery, opening valves 14 and 16 to add liquid131I desorption, desorption131The solution I enters a distiller 5 for heating, purifying and distilling131I. Purifying the distilled131And I, collecting the product in a purification column 8, subpackaging the product, and opening a valve 13 to enable the heated and distilled tail gas to enter a gas storage tank 9 for storage. And closing all valves after the work is finished.
And tail gas generated in the processes of extraction, elution, distillation and purification is completely collected into the gas storage tank 9 for storage, and is discharged after being detected to be qualified.
It will be apparent to those skilled in the art that various changes and modifications can be made in the present disclosure without departing from the spirit and scope of the disclosure. Thus, if such modifications and variations to the present disclosure fall within the scope of the claims of the present disclosure and their equivalents, it is intended that the present disclosure also encompass such modifications and variations. The foregoing examples or embodiments are merely illustrative of the present disclosure, which may be embodied in other specific forms or in other specific forms without departing from the spirit or essential characteristics thereof. The described embodiments are, therefore, to be considered in all respects as illustrative and not restrictive. The scope of the disclosure should be indicated by the appended claims, and any changes that are equivalent to the intent and scope of the claims are intended to be included within the scope of the disclosure.
Claims (10)
1. Extraction from dissolved irradiated uranium target tail gas131I, characterized in that it comprises: a gas blowing cylinder (1), an acid feeding liquid tank (19), a dissolver (2), a liquid absorption column (3), an elution liquid tank (15), an anion exchange resin column (4), a distiller (5), a distiller heater (6), a product bottle (7), a purification column (8) and a gas storage tank (9);
wherein the gas blowing cylinder (1) is respectively connected with the acid feeding liquid tank (19) and the dissolver (2) through pipelines; the acid feeding liquid tank (19) is connected with the dissolver (2) through a pipeline; a feeding pipeline is arranged on the acid feeding liquid tank (19), and a valve is arranged on the feeding pipeline; the dissolver (2) is connected with the liquid absorption column (3) through a pipeline; the liquid absorption column (3) is respectively connected with the anion exchange resin column (4), the gas storage tank (9) and the purification column (8) through pipelines; the anion exchange resin column (4) is connected with the distiller (5) through a pipeline; the elution material liquid tank (15) is connected with the anion exchange resin column (4) through a pipeline, a material inlet pipeline is arranged at the top of the elution material liquid tank (15), and a valve is arranged on the pipeline; a distiller heater (6) is arranged at the bottom of the distiller (5); the distiller (5) is connected with the purification column (8) through a pipeline; the purification column (8) is respectively connected with the product bottle (7) and the gas storage tank (9) through pipelines; the air storage tank (9) is provided with an exhaust pipeline, and the product bottle (7) is positioned in the cold trap.
2. Extraction from dissolved irradiated uranium target tail gas according to claim 1131The device is characterized in that the gas blowing cylinder (1) is filled with high-purity gas, and the high-purity gas is 99% of inert gas.
3. Extraction from dissolved irradiated uranium target tail gas according to claim 1131The device is characterized in that a connecting pipeline of the gas drum (1) and the dissolver (2) extends to the bottom of the dissolver (2).
4. Extraction from dissolved irradiated uranium target tail gas according to claim 1131The device I is characterized in that a sieve plate (25) is arranged at the bottom of the liquid absorption column (3), and alkaline liquid is arranged in the liquid absorption column (3).
5. Extraction from dissolved irradiated uranium target tail gas according to claim 1131The device is characterized in that an eluent is filled in the eluent liquid tank (15), and the eluent is alkaline liquid.
6. Extraction from dissolved irradiated uranium target tail gas according to claim 1131The device I is characterized in that the number of the liquid absorption columns (3) is more than or equal to 1, and when the number of the liquid absorption columns (3) is more than 1, the liquid absorption columns (3) are connected in series.
7. Extraction from dissolved irradiated uranium target tail gas according to claim 1131The device of I is characterized in that the bottom of the liquid absorption column (3) is provided with an alkaline liquid discharge port.
8. Extraction from dissolved irradiated uranium target tail gas according to claim 1131The device is characterized in that valves are arranged on connecting pipelines of the gas blowing cylinder (1), the acid feed liquid tank (19) and the dissolver (2); a valve is arranged on a connecting pipeline of the acid feeding liquid tank (19) and the dissolver (2); a valve is arranged on a connecting pipeline of the dissolver (2) and the liquid absorption column (3); valves are arranged on the connecting pipelines of the liquid absorption column (3), the purification column (8) and the gas storage tank (9); a control valve is arranged on a connecting pipeline of the elution material liquid tank (15) and the anion exchange resin column (4)A valve for controlling the feeding speed of the eluent liquid tank (15); and a valve is arranged on an exhaust pipeline of the gas storage tank (9).
9. Extraction from dissolved irradiated uranium target tail gas according to claim 1131The device I is characterized in that pressure gauges (11, 24) are arranged on the gas blowing cylinder (1) and the gas storage tank (9).
10. Extraction from tail gas of dissolved irradiated uranium target according to claim 4, 5 or 7131The device of I is characterized in that the alkaline liquid is sodium hydroxide solution, potassium hydroxide solution or ammonia water, and the pH value is>10。
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN111068482A (en) * | 2020-01-07 | 2020-04-28 | 中国原子能科学研究院 | Extraction from dissolved irradiated uranium target tail gas131I apparatus |
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| CN111068482A (en) * | 2020-01-07 | 2020-04-28 | 中国原子能科学研究院 | Extraction from dissolved irradiated uranium target tail gas131I apparatus |
| CN111068482B (en) * | 2020-01-07 | 2024-09-06 | 中国原子能科学研究院 | Extraction from dissolved irradiation uranium target tail gas131I device |
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