CN105336386A - Anti-radiation apparatus for nuclear medicine synthetic process - Google Patents
Anti-radiation apparatus for nuclear medicine synthetic process Download PDFInfo
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- CN105336386A CN105336386A CN201410391403.3A CN201410391403A CN105336386A CN 105336386 A CN105336386 A CN 105336386A CN 201410391403 A CN201410391403 A CN 201410391403A CN 105336386 A CN105336386 A CN 105336386A
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- nuclear medicine
- shielding
- protective seam
- resin column
- waste
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- Nuclear Medicine (AREA)
- Radiation-Therapy Devices (AREA)
Abstract
The invention discloses an anti-radiation apparatus for a nuclear medicine synthetic process. A resin column filled with resin is placed in an anti-radiation container to absorb radioisotope ions in water and convert liquid waste into solid wastes, so treatment is facilitated; and damage to medical workers can be avoided. The anti-radiation apparatus for the nuclear medicine synthetic process is advantaged by simple operation and great protection effect, thereby being able to be applied to PET image agent synthetic field.
Description
Technical field
The invention belongs to the field of nuclear medicine, be specifically related to a kind of shielding.
Background technology
The synthesis flow of traditional PET developer FDG molecule is as follows: with accelerator, oxygen-18 water is bombarded into band active fluorine 18 negative ion
18f
-, now have some subsidiary reactions, because target is metal material, can be produced some be with active metal cation under the bombardment of proton.The liquid that accelerator bombarded is transmitted through QMA post, in solution
18f
-be adsorbed on QMA post, but the kation in solution is not adsorbed by QMA post, liquid enters oxygen-18 water waste liquid bottle after QMA post.
Because these are with the active metal cation half life period very long, hospital faces severe Medical Personnel Protection and the problem of treat liquid radioactivity Biohazard Waste.In waste liquid bottle, liquid has radioactivity, is inevitably subject to the irradiation of ray, causes the generation of radiation sickness in the course of time when waste liquid bottle takes out by medical personnel from synthesis hot cell.The preservation difficulty of radioactive liquid discarded object is very large, cost is very high, just in case container leakage radioactive liquid to be mixed into ground water regime consequence hardly imaginable.
Number of patent application be 200720003456.9 Chinese patent disclose a kind of SPECT radiocontamination intelligent protection system for medical purpose, be made up of hardware setting system and intelligent control system.Hardware setting system is made up of degrade ponds and ionizing-radiation sensor, liquid level sensor, solenoid valve, positive displacement pump of four nuclear wastes, and intelligent control system is made up of computer (comprising display printer) and intelligent control software, interface circuit and field control center.The nuclear waste using 131 iodine and 99M technetium to produce for SPECT carries out intellectuality protection to environment.Its technical characteristic is presented as: ionizing-radiation sensor is all laid in order to monitor nuclear waste decay situation in pond of 1. degrading, 2. nuclear waste leakage ionizing-radiation sensor is laid in order to monitor nuclear waste leakage situation in degraded outside, pond, 3. liquid level sensor is laid in order to monitor nuclear waste liquid level in degraded pond, 4. solenoid valve is opened draining etc. that is closed, dredge pump and is controlled by computer full-automatic, and 5. whole nuclear waste protective treatment system is omnidistance intelligently runs and display in real time.
The patent No. is that CN203108581U discloses a kind of nuclear medicine radiation proof test tube rack, design a kind of test tube rack, connected the bottom surfaces of stereotype body by screw in the corner, upper end of plumbous box body, multiple circular hole or square hole is arranged with in the middle part of described plumbous body, the cavity of described multiple circular hole or the corresponding plumbous box body of square hole, plumbous upper cover is buckled in the top of stereotype body, and plumbous upper cover covers on all circular holes or square hole; This utility model, by using plumbous box body, stereotype body and plumbous upper cover by totally-enclosed for invisible spectro radiomaterial, makes the radiomaterial preventing or shift to damage medical personnel, effectively prevent the damage of radioactive material confrontation medical personnel.
Summary of the invention
Based on prior art, need a kind of medical personnel of protection safety badly and the device making radioactive waste completely controlled.In order to solve to the damage problem that radiomaterial can not well collect and avoid radioactive material confrontation human body to bring in prior art, the present invention proposes a kind of shielding, effectively can play protection medical personnel safety.Technical scheme of the invention process is as follows:
A kind of for the shielding in nuclear medicine building-up process; it is arranged between product collecting device and waste collecting device; comprise protective seam and for absorbing radioisotopic resin column in waste liquid; resin column is located in protective seam, and protective seam all with product collecting device is connected with waste collecting device with resin column two ends.
Further, described protective seam is tubulose or column, is detachable structure, and this protective layer is a cylindrical shape, and this protective layer has certain thickness, for convenience of placing, also can be square column shape;
The removable place of described protective seam is with being threaded, and also can adopt clip, the modes such as rivet connect;
Described protective seam is made up of metallic lead or tungsten;
Further, described protective seam two ends are also provided with closes cover, and due to when applying, radiation proof protective layer two ends need to be connected with QMA post, waste liquid bottle, then this protective layer needs two ends perforate.Ray is slightly revealed at position of opening, but people stand in side operation can guarantee safety.After developer building-up process terminates, for guaranteeing safety, two ends connecting hose can be pulled out, buckling the closed cover at two ends, preventing the leakage of two ends position of opening ray.The screw thread turning on plumbous protective layer processed for convenience, to abandon the radioactive resin column of the band used, designs: there are two ribs protruded at radiation proof protective layer two ends as shown in Figure 1 and Figure 2, and closed cover corresponding positions is equipped with two grooves, conveniently connects and uses.
Described closed cover is made by by metallic lead or tungsten.
Be provided with resin column Adsorption of Radioactive isotope in this device, liquid given up and becomes solid waste, the intractability that the intractability of radioactivity solid waste wants specific activity liquid useless is much smaller, cost is much lower.Meanwhile, this shielding also can stop ray diffusion outwardly, protection of the environment.
The Advantageous Effects of the shielding that the present invention proposes is:
1., before synthesizing developer, the pipeline journey connected mode adding the postpone of this radiation-proof clothes is only a multi-link shielding between QMA post and waste liquid bottle, and remainder is identical with origin operation flow process.
2. this device does not affect normal developer synthetic operation.
3. after developer end of synthesis, pull out the flexible pipe at shielding two ends, put the closed cover at two ends, above radioactivity solid waste dustbin, turn on this shielding, make to fall into dustbin with radioisotopic resin column by gravity, notice that this process need carry out suitable protection.
4. apparatus structure of the present invention use simple to operation.
It is to be noted, the shielding reusable edible of plumbous system or tungsten, and according in resin column fill the difference of amount of resin, degree that different accelerator comes off isotopic ion is different, the adsorbance of resin and can access times different, the replacing of resin column should be carried out within the safe time limit.
Accompanying drawing explanation
Fig. 1 protective layer schematic diagram
Fig. 2 closes cover schematic diagram
Fig. 3 resin column schematic perspective view
Fig. 4 resin column side view
Embodiment
Specific embodiment 1
Embodiment 1
As shown in Figure 1, plumbous protective layer length 8cm processed, internal diameter 1.5cm, external diameter 3cm, two ends connecting hole diameter 0.8cm, outer lug height 3mm, screw thread adopts three start screw line, can turn on fast.
Plumbous end socket length 2cm processed, internal diameter 3.1cm, external diameter 4cm, depth of groove 3.5mm.
Resin column is built with resin cation and resin anion (R.A.).
Embodiment 2
Tungsten protective layer length 8cm, internal diameter 1.5cm, external diameter 3cm, two ends connecting hole diameter 0.8cm, outer lug height 3mm, screw thread adopts three start screw line, can turn on fast.
Tungsten end socket length 2cm, internal diameter 3.1cm, external diameter 4cm, depth of groove 3.5mm.
Resin column is built with resin cation.
Embodiment 3
Plumbous protective layer length 8cm processed, internal diameter 1.5cm, external diameter 3cm, two ends connecting hole diameter 0.8cm, outer lug height 3mm, screw thread adopts three start screw line, can turn on fast.
Resin column is built with resin cation.
Claims (6)
1. one kind for the shielding in nuclear medicine building-up process; it is arranged between product collecting device and waste collecting device; it is characterized in that comprising protective seam and for absorbing radioisotopic resin column in waste liquid; resin column is located in protective seam, and protective seam all with product collecting device is connected with waste collecting device with resin column two ends.
2. according to claim 1 for the shielding in nuclear medicine building-up process, it is characterized in that protective seam is tubulose or column, is detachable structure.
3. according to claim 2 for the shielding in nuclear medicine building-up process, it is characterized in that the removable place of protective seam is with to be threaded or draw-in groove connects.
4. any one of claim 1-3 described in claim for the shielding in nuclear medicine building-up process, it is characterized in that protective seam two ends be also provided with close cover.
5. according to claim 4 for the shielding in nuclear medicine building-up process, it is characterized in that protective seam is made up of metallic lead or tungsten.
6. according to claim 4 for the shielding in nuclear medicine building-up process, it is characterized in that closing cover makes by by metallic lead or tungsten.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410391403.3A CN105336386A (en) | 2014-08-11 | 2014-08-11 | Anti-radiation apparatus for nuclear medicine synthetic process |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410391403.3A CN105336386A (en) | 2014-08-11 | 2014-08-11 | Anti-radiation apparatus for nuclear medicine synthetic process |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN105336386A true CN105336386A (en) | 2016-02-17 |
Family
ID=55286853
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201410391403.3A Pending CN105336386A (en) | 2014-08-11 | 2014-08-11 | Anti-radiation apparatus for nuclear medicine synthetic process |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN105336386A (en) |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2006184045A (en) * | 2004-12-27 | 2006-07-13 | Ebara Kogyo Senjo Kk | Ion-exchange resin tower for chemical decontamination |
| CN101475629A (en) * | 2009-01-15 | 2009-07-08 | 上海化工研究院 | Preparation of stable isotope 15N labeling octapeptide GFL |
| CN102391318A (en) * | 2011-08-22 | 2012-03-28 | 常熟华益化工有限公司 | Fluorine-18 fluorodeoxyglucose (18F-FDG) kit and application thereof in synthesis of positron emission tomography (PET) developer FDG |
| CN202382970U (en) * | 2011-11-18 | 2012-08-15 | 国核电力规划设计研究院 | Liquid-gas sampling system |
-
2014
- 2014-08-11 CN CN201410391403.3A patent/CN105336386A/en active Pending
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2006184045A (en) * | 2004-12-27 | 2006-07-13 | Ebara Kogyo Senjo Kk | Ion-exchange resin tower for chemical decontamination |
| CN101475629A (en) * | 2009-01-15 | 2009-07-08 | 上海化工研究院 | Preparation of stable isotope 15N labeling octapeptide GFL |
| CN102391318A (en) * | 2011-08-22 | 2012-03-28 | 常熟华益化工有限公司 | Fluorine-18 fluorodeoxyglucose (18F-FDG) kit and application thereof in synthesis of positron emission tomography (PET) developer FDG |
| CN202382970U (en) * | 2011-11-18 | 2012-08-15 | 国核电力规划设计研究院 | Liquid-gas sampling system |
Non-Patent Citations (1)
| Title |
|---|
| 刘标 等: "国产与进口富氧水、FDG试剂盒合成18F-FDG的结果比较", 《中国临床医学影像杂志》 * |
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Application publication date: 20160217 |
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| WD01 | Invention patent application deemed withdrawn after publication |