CN217947656U - Radionuclide ion distribution system - Google Patents

Radionuclide ion distribution system Download PDF

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Publication number
CN217947656U
CN217947656U CN202121508772.8U CN202121508772U CN217947656U CN 217947656 U CN217947656 U CN 217947656U CN 202121508772 U CN202121508772 U CN 202121508772U CN 217947656 U CN217947656 U CN 217947656U
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way valve
dilution water
distribution system
stock solution
nuclide
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马扶雷
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Tianjin Mifumei Technology Development Co ltd
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Tianjin Mifumei Technology Development Co ltd
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Abstract

The utility model discloses a radionuclide ion distribution system, including stock solution device, multi-way valve, waste liquid collection device, dilution water device, syringe pump, two-way valve, gas device, be provided with on the multi-way valve with the nuclide ion receiving port of the nuclide ion output end intercommunication of stock solution device, with the waste liquid discharge port of waste liquid collection device intercommunication, with the dilution water receiving port of dilution water device intercommunication, with the injection port and a plurality of nuclide ion partial shipment port of two-way valve intercommunication, the syringe pump intercommunication the two-way valve, the two-way valve intercommunication the gas device. Through the arrangement of the stock solution device and the dilution water device, the nuclide ion stock solution can be diluted in any proportion according to needs and then is subpackaged for different synthesizers for use, and resources are greatly saved. Through the setting of waste liquid collection device and dilution water device, can wash multi-ported valve and all pipelines, avoid remaining nuclide ion in it to cause next partial shipment inaccurate.

Description

Radionuclide ion distribution system
Technical Field
The utility model belongs to the technical field of medical science experimental facilities, specifically be a radionuclide ion distribution system.
Background
The radio-labeled drugs obtained by labeling with radionuclides are the most commonly used PET radiopharmaceuticals (also called imaging agents), and have been widely used in PET imaging studies for tumors, cardiovascular diseases and neuropsychiatric diseases, so that the demand for radionuclide ions and the demand for quantitative labeling are continuously increased. Radionuclides such as 18F, 11C, and 13N are generally manufactured by a cyclotron, and then labeled onto different chemical substrates by a chemical synthesis module (also called synthesizer) to synthesize various final radiopharmaceuticals for clinical use. Because the positron radioactive drug has the characteristics of high radioactivity and short half-life, the positron radioactive drug is fully automatically synthesized by a chemical synthesis module by using trace reagents.
E.g. 18F radionuclides, cyclotron pass 18 O(p,n) 18 The F nuclear reaction, the application of small volume 18 O]H 2 And O target, continuously bombarding the target by a certain proton beam. Pneumatically transferring 18F-F - Transferring to an automated chemical synthesis module, 18F-F - Adsorbed onto QMA column, and poured into reaction tube for subsequent synthesis reaction. Automated synthesis of modules, according to the target water volume (H) used by the modules 2 18 O) is fixed, about 2-5mL, and radioactive reactive nuclides 18F-F delivered by the automated synthesis module - All are untreated, and only one reaction can be carried out after each target transfer, so that 18F-F is obtained in each reaction - Only one developer can be synthesized, which results in a great waste.
At present, aiming at the component use of fluorinion, most synthesis modules used in hospitals are new-generation products, and the method has the remarkable characteristics of high system integration level, stable synthesis process, short production time, obviously improved yield of products in earlier stages and the like. Therefore, most of the centers of the accelerators have the problem that the actual nuclide demand is less than the maximum output of the equipment, or the accelerator needs to be started up twice when two developers are synthesized on different synthesis modules, and the two conditions cause resource waste, and the maximum reason is that the accelerator passes through the targetWater (H) 2 18 O) is a one-time pass out that cannot separate out unwanted nuclides or target water for use in different synthesis modules.
Chinese patent document CN203568823U discloses an automatic fluoride ion split charging device, which comprises a collecting bottle, a first control valve, a second control valve, a quantitative injection pump and a collecting and distributing valve, which are connected in sequence, wherein the collecting and distributing valve is provided with a plurality of passages capable of being independently started along the axial direction, and the passages are respectively connected with corresponding split charging bottles to realize the metering and split charging of fluoride ion solution.
However, the fluorine ion dispensing apparatus disclosed in the above-mentioned chinese patent document has a complicated structure and is inconvenient to control because a plurality of control valves are provided. In addition, the conventional radionuclide ion dispensing device cannot discharge the liquid remaining in the dispensing valve after one dispensing operation, thereby affecting the accuracy of the metering.
SUMMERY OF THE UTILITY MODEL
The utility model aims to overcome the defects in the prior art and provide a radionuclide ion distribution system to solve the problems of complicated structure and low metering precision caused by residual liquid in the prior art.
In order to solve the technical problem the utility model provides a technical scheme is:
a radionuclide ion distribution system comprises a stock solution device, a multi-way valve, a waste solution collecting device, a dilution water device, an injection pump, a two-way valve and a gas device, wherein the multi-way valve is provided with a nuclide ion receiving port communicated with a nuclide ion output end of the stock solution device, a waste solution discharge port communicated with the waste solution collecting device, a dilution water receiving port communicated with the dilution water device, an injection port communicated with the two-way valve and a plurality of nuclide ion subpackaging ports, the injection pump is communicated with the two-way valve, and the two-way valve is communicated with the gas device.
By adopting the technical scheme, the nuclide ion receiving port, the dilution water receiving port and the injection port on the multi-way valve are opened, the injection pump sequentially passes through the two-way valve and the multi-way valve to extract radionuclide ion stock solution from the stock solution device, extract dilution water from the dilution water device and extract certain boosting air, then the nuclide ion receiving port, the dilution water receiving port and the injection port are closed, any nuclide ion subpackaging port is opened, the stock solution, the dilution water and the boosting air in the injection pump are pushed into the corresponding subpackaging channel, and then the normally closed port of the two-way valve is opened, so that compressed gas in the gas device escapes and pushes the dilution stock solution, and the dilution stock solution is conveyed to the synthesizer. After all partial shipment works, can open dilution water at any time and receive port and injection port for the injection pump can extract the dilution water and wash the multi-way valve and all pipelines of being connected with the multi-way valve in proper order, and this cleaning process suggestion is gone on after the partial shipment, if wash before the partial shipment, then need change the stoste device after the washing, avoids wasing the waste liquid and gets into to the stoste device. Preferably, the stock solution device, the waste solution collecting device, the dilution water device, preferably a sealed container to avoid contamination, such as a vial with a rubber stopper.
Furthermore, the capacity of the stock solution device is 10-30 ml, and the capacity of the waste solution collecting device is 1000ml.
Furthermore, the nuclide ion split charging port is connected with a synthesizer.
Further, the number of the synthesizers is equal to or greater than three. I.e. supporting at least the transmission of 3 synthesizers, i.e. the multi-way valve is at least a six-way valve. The synthesizer is used for further synthesizing the separated radionuclide ions into the medicine.
Furthermore, the synthesizer is arranged in hot chambers, and an opening and closing safety interlocking device is arranged between the hot chambers.
Furthermore, the safety locking device is an alarm bell or an alarm lamp. That is, after each split charging, only one synthesizer is in operation, and when other synthesizers are turned on, a warning light is turned on or an alarm is sounded.
Further, a dose calibrator is disposed on the syringe pump.
Further, the dose calibrator has a maximum measurement of 20Ci, i.e. the dose calibrator can measure 20Ci of radionuclide ions at maximum.
Further, a proportion regulating valve is arranged between the two-way valve and the gas device, and the pressure of the transmission gas can be regulated.
Further, the nuclide ion input end of the stock solution device is communicated with the cyclotron.
Furthermore, the valve cores of the multi-way valve and the two-way valve are made of sapphire materials, and are corrosion-resistant and wear-resistant.
Further, the power requirement of the radionuclide ion distribution system is 110-220V, the power is 300W, and the system gas requirement is at least 70Psi of gas pressure.
Furthermore, a liveness meter and a liquid level sensor are arranged in the stock solution device, the activity of the radioactive nuclide ions is measured through the liveness meter, and the liquid height is measured through the liquid level sensor.
Furthermore, the gas device is internally provided with one of compressed air, nitrogen and argon. Among them, nitrogen or argon is preferable, and the compressed air is filtered clean air.
The output end of the controller is respectively electrically connected with the nuclide ion receiving port, the waste liquid discharge port, the dilution water receiving port, the injection port and a plurality of nuclide ion subpackaging ports on the multi-way valve, the injection pump, the two-way valve, the gas device, the stock solution device, the waste liquid collecting device and the dilution water device, and the input end of the controller is respectively electrically connected with the activity meter, the liquid level sensor, the safety interlocking device, the dose calibrator and the proportion regulating valve.
The utility model discloses following beneficial effect has:
1. the utility model discloses a setting of stoste device and dilution water device can carry out the dilution of arbitrary proportion as required to the stoste and use for the synthesizer of difference with the partial shipment, has practiced thrift the resource greatly, improves nuclide ion's availability factor.
2. The utility model discloses a setting of waste liquid collection device and dilution water device can wash multi-ported valve and all pipelines, avoids manual abluent complex operation and easily makes mistakes, and the clean sanitary problem of the transmission line of assurance avoids remaining the nuclide ion and causes the next partial shipment inaccurate.
Drawings
FIG. 1 is a schematic view of a radionuclide ion distribution system according to embodiment 1;
FIG. 2 is a schematic diagram of the controller connection of the radionuclide ion distribution system of embodiment 2;
FIG. 3 is a schematic view of the radionuclide ion distribution system according to embodiment 3;
FIG. 4 is a schematic view of the internal structure of embodiment 3.
In the figure: 1. a stock solution device; 2. a multi-way valve; 201. a nuclide ion receiving port; 202. a waste liquid discharge port; 203. a dilution water receiving port; 204. an injection port; 205. a nuclide ion split charging port; 3. a waste liquid collection device; 4. a dilution water unit; 5. an injection pump; 6. a two-way valve; 7. a gas device; 8. a synthesizer; 9. a cyclotron; 10. a hot chamber; 11. a safety interlock device; 12. a dose calibrator; 13. a proportional regulating valve; 14. a groove-type photoelectric switch infrared inductor; 15. a controller; 16. an activity meter; 17. a liquid level sensor; 18. a box body; 19. a top plate; 20. a syringe support; 21. an upper pressure plate; 22. pressing a plate; 23. a stepping motor mounting plate; 24. placing the plate; 25. hooking; 26. a conduit; 27. a through groove; 28. a screw rod; 29. a stepping motor; 30. a screw rod mounting block; 31. a guide rail; 32. a slider; 33. the sensor is provided with an adjusting plate.
Detailed Description
The present invention will be described in detail with reference to the accompanying drawings and examples.
Example 1
A radionuclide ion distribution system is shown in figure 1 and comprises a stock solution device 1, a multi-way valve 2, a waste solution collecting device 3, a dilution water device 4, an injection pump 5, a two-way valve 6 and a gas device 7, wherein the multi-way valve 2 is provided with a nuclide ion receiving port 201 communicated with a nuclide ion output end of the stock solution device 1, a waste solution discharge port 202 communicated with the waste solution collecting device 3, a dilution water receiving port 203 communicated with the dilution water device 4, an injection port 204 communicated with the two-way valve 6 and three nuclide ion split charging ports 205, the injection pump 5 is communicated with the two-way valve 6, the two-way valve 6 is communicated with the gas device 7 through a proportion regulating valve 13, and compressed argon gas is filled in the gas device 7. The nuclide ion dispensing port 205 is connected to the synthesizer 8. The number of the synthesizer 8 is three, and the multi-way valve 2 is a six-way valve. The synthesizer 8 is arranged in the hot chamber 10, a starting and stopping safety interlocking device 11 is arranged between the hot chambers 10, and the starting and stopping safety interlocking device 11 is an alarm bell or a warning lamp. A dose calibrator 12 is provided on the syringe pump 5, the maximum measurement value of the dose calibrator 12 being 20Ci. The nuclide ion input end of the stock solution device 1 is communicated with the cyclotron 9. The valve cores of the multi-way valve 2 and the two-way valve 6 are made of sapphire materials.
When the device works, the nuclide ion receiving port 201, the dilution water receiving port 203 and the injection port 204 on the multi-way valve 2 are opened, the injection pump 5 sequentially passes through the two-way valve 6 and the multi-way valve 2 to extract stock solution from the stock solution device 1, extract dilution water from the dilution water device 4 and extract certain boosting air, then the nuclide ion receiving port 201, the dilution water receiving port 203 and the injection port 204 are closed, any nuclide ion subpackaging port 205 is opened, the stock solution, the dilution water and the boosting air in the injection pump 5 are pushed into corresponding subpackaging channels, then the normally closed port of the two-way valve 6 is opened, compressed argon in the gas device 7 is controlled and released through the proportion adjusting valve 13 to push the diluted stock solution to be transmitted, and the diluted stock solution is sent into the synthesizer 8. The use of the boost air enables no liquid residue to be left in the injection pump 5 after the injection pump pushes the diluent, the subpackage dosage is accurately controlled, and the boost air can be obtained from the waste liquid discharge port 202 communicated with the waste liquid collecting device 3. All partial shipment finishes and synthesizer 8 has been worked and transmits finished product medicine to the partial shipment hot chamber after, opens dilution water receiving port 203 and injection port 204 for injection pump 5 can extract the dilution water and wash multi-way valve 2 and all pipelines of being connected with multi-way valve 2, closes dilution water receiving port 203 at last, opens waste liquid discharge port 202, makes injection pump 5 can be with washing waste liquid propelling movement to waste liquid collection device 3 in. This cleaning process is recommended to be performed after the dispensing is completed, and if the cleaning is performed before the dispensing, the stock solution apparatus 1 needs to be replaced after the cleaning is completed.
Example 2
A radionuclide ion distribution system is different from the embodiment 1 in that an activity meter 16 and a liquid level sensor 17 are arranged in a stock solution device 1, a multi-way valve 2 is an eight-way valve, and four nuclide ion dispensing ports 205 of the multi-way valve 2 are respectively connected with a synthesizer 8. The two-way valve 6 is directly communicated with a gas device 7, and compressed nitrogen is filled in the gas device 7. The device also comprises a controller 15, as shown in fig. 2, the output end of the controller 15 is respectively electrically connected with a nuclide ion receiving port 201, a waste liquid discharge port 202, a dilution water receiving port 203, an injection port 204, four nuclide ion subpackaging ports 205, an injection pump 5, a two-way valve 6, a gas device 7, a stock solution device 1, a waste liquid collecting device 3 and a dilution water device 4 on the multi-way valve 2, and the input end of the controller 15 is respectively electrically connected with an activity meter 16, a liquid level sensor 17, a safety interlocking device 11 and a dose calibrator 12.
The activity meter 16, the liquid level sensor 17, the safety interlocking device 11 and the dose calibrator 12 can respectively transmit signals obtained by the activity meter, the liquid level sensor 17, the safety interlocking device 11 and the dose calibrator 12 to the controller 15, and the controller 15 transmits instructions to each port on the multi-way valve 2, the injection pump 5, the two-way valve 6, the gas device 7, the stock solution device 1, the waste solution collecting device 3 and the dilution water device 4 according to the received signals so as to perform corresponding dilution or subpackage or cleaning work.
Example 3
A radionuclide ion distribution system is shown in the schematic structural diagrams of fig. 3 and 4, and comprises a box body 18, wherein a multi-way valve 2, a two-way valve 6, a top plate 19, a placing plate 24 and a hook 25 are arranged outside the box body 18, a control box is arranged inside the box body 18, and a screw rod mounting block 30, a guide rail 31 and a sensor mounting adjusting plate 33 are arranged on a panel of the control box opposite to the top plate 19. An injector support 20 is installed on a top plate 19, the middle of an injection pump 5 is installed on the injector support 20 through an upper pressure plate 21 and a bolt, the upper end of the injection pump 5 is installed on a stepping motor installation plate 23 through a pressure plate 22 and a bolt, the other end of the stepping motor installation plate 23 penetrates through a through groove 27 in a box body 18 and is installed on a sliding block 32, the sliding block 32 is connected on a guide rail 31 in a sliding mode, a stepping motor 29 and a lead screw 28 are installed below the stepping motor installation plate 23, two ends of the lead screw 28 are installed on a lead screw installation block 30, and a groove type photoelectric switch infrared inductor 9 is installed between the lead screw installation block 30 and a sensor installation adjusting plate 33. The placing plate 24 is provided with the stock solution device 1 and the waste solution collecting device 3, and the hook 25 is hung with the dilution water device 4. The stock solution device 1, the waste solution collecting device 3, the dilution water device 4, the injection pump 5, the two-way valve 6, the multi-way valve 2 and the synthesizer 8 are communicated through a conduit 26. The two-way valve 6 is also connected to a gas device 7 (not shown) via a conduit 26. Wherein the stock solution device 1 is a penicillin bottle 1 with a rubber plug, and the capacity is 10-30 ml; the waste liquid collecting device 3 is 1 penicillin bottle with rubber plug, the capacity is 1000ml, and the number of the synthesizer 8 is 3 (not completely shown in the figure); the dilution water device 4 is a dilution water bag. The electric power requirement of the system is 110-220V of voltage and 300W of power, and the gas requirement of the system is that the gas pressure is at least 70Psi. Preferably, the two ends of the conduit 26 for infusion are connected with luer connectors, the other end of each luer connector is connected with a port of the penicillin bottle or the multi-way valve 2 or a port of the two-way valve 6 or a port of the dilution water device 4, and the conduit 26 is in threaded connection due to the use of the luer connectors, so that the conduit 26 is convenient to replace. The infusion catheters 26 connected with the penicillin bottles are all connected with needles which penetrate through the rubber plugs and extend into the penicillin bottles to extract liquid. Still be connected with the pipe 26 that is used for the exhaust on the xiLin bottle, be used for carminative pipe 26 one end to pass the rubber buffer and stretch into to xiLin bottle in, the other end passes through filter intercommunication atmosphere, the setting of pipe 26 for the exhaust makes xiLin bottle internal gas pressure unanimous with atmospheric pressure, both is convenient for syringe pump 5 to draw liquid or release liquid, also is convenient for avoid atmospheric pollution liquid (luer joint, syringe needle, be used for carminative pipe 26, filter are all current, do not need to describe in many times, also all do not show in figure 3).
The stepping motor 29 rotates to drive the screw rod 28 to rotate, so that the stepping motor mounting plate 23 drives the injection pump 5 to move up and down under the longitudinal limitation of the slide block 32 and the guide rail 31 so as to perform pumping work, namely the acquisition of stock solution, gas and dilution water and the subpackaging work of the dilution water, the arrangement of the groove-shaped photoelectric switch infrared inductor 9 can accurately acquire and control the moving distance of the stepping motor 29, namely the moving distance of the stepping motor mounting plate 23, and further the pumping and discharging amount of the injection pump 5 can be accurately controlled.
It should be finally noted that the above embodiments are only used for illustrating the technical solutions of the embodiments of the present invention and not for limiting the same, and although the embodiments of the present invention are described in detail with reference to the preferred embodiments, those skilled in the art should understand that the technical solutions of the embodiments of the present invention can still be modified or replaced with equivalents, and these modifications or equivalent replacements cannot make the modified technical solutions depart from the scope of the technical solutions of the embodiments of the present invention.

Claims (10)

1. The radionuclide ion distribution system is characterized by comprising a stock solution device (1), a multi-way valve (2), a waste solution collecting device (3), a dilution water device (4), an injection pump (5), a two-way valve (6) and a gas device (7), wherein the multi-way valve (2) is provided with a nuclide ion receiving port (201) communicated with a nuclide ion output end of the stock solution device (1), a waste solution discharge port (202) communicated with the waste solution collecting device (3), a dilution water receiving port (203) communicated with the dilution water device (4), an injection port (204) communicated with the two-way valve (6) and a plurality of nuclide ion subpackaging ports (205), the injection pump (5) is communicated with the two-way valve (6), and the two-way valve (6) is communicated with the gas device (7);
the automatic feeding device is characterized by further comprising a box body (18), wherein a multi-way valve (2), a two-way valve (6), a top plate (19), a placing plate (24) and a hook (25) are arranged outside the box body (18), a control box is arranged inside the box body (18), and a screw rod mounting block (30), a guide rail (31) and a sensor mounting adjusting plate (33) are arranged on a panel of the control box opposite to the top plate (19); an injector support (20) is mounted on a top plate (19), the middle of an injection pump (5) is mounted on the injector support (20) through an upper pressing plate (21) and a bolt, the upper end of the injection pump (5) is mounted on a stepping motor mounting plate (23) through a pressing plate (22) and a bolt, the other end of the stepping motor mounting plate (23) penetrates through a through groove (27) in a box body (18) and is mounted on a sliding block (32), the sliding block (32) is connected onto a guide rail (31) in a sliding manner, a stepping motor (29) and a lead screw (28) are mounted below the stepping motor mounting plate (23), two ends of the lead screw (28) are mounted on a lead screw mounting block (30), and a groove-shaped photoelectric switch infrared inductor (14) is mounted between the lead screw mounting block (30) and a sensor mounting adjusting plate (33); a stock solution device (1) and a waste liquid collecting device (3) are arranged on the placing plate (24), and a dilution water device (4) is hung on the hook (25); the stock solution device (1), the waste liquid collecting device (3), the dilution water device (4), the injection pump (5), the two-way valve (6), the multi-way valve (2) and the synthesizer (8) are communicated through a conduit (26).
2. The radionuclide ion distribution system according to claim 1, characterized in that the nuclide ion dispensing port (205) is connected to a synthesizer (8).
3. The radionuclide ion distribution system according to claim 2, characterized in that the number of the synthesizers (8) is equal to or greater than three.
4. The radionuclide ion distribution system according to claim 2, characterized in that the synthesizer (8) is disposed in a hot chamber (10), and an open/close safety interlock (11) is provided between the hot chambers (10).
5. The radionuclide ion distribution system according to claim 4, characterized in that the on-off safety interlock (11) is an alarm bell or warning light.
6. The radionuclide ion distribution system according to claim 1, characterized in that a dose calibrator (12) is provided on the syringe pump (5).
7. The radionuclide ion distribution system according to claim 6, characterized in that the maximum measured value of the dose calibrator (12) is 20Ci.
8. The radionuclide ion distribution system according to claim 1, characterized in that a proportional control valve (13) is provided between the two-way valve (6) and the gas device (7).
9. The radionuclide ion distribution system according to claim 1, characterized in that the nuclide ion input of the stock solution arrangement (1) communicates with a cyclotron (9).
10. The radionuclide ion distribution system according to claim 1, characterized in that the multi-way valve (2) and the spool of the two-way valve (6) are made of sapphire.
CN202121508772.8U 2021-07-02 2021-07-02 Radionuclide ion distribution system Active CN217947656U (en)

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