CN107293346A - A kind of Sn 113/In 113m generators and preparation method - Google Patents
A kind of Sn 113/In 113m generators and preparation method Download PDFInfo
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- CN107293346A CN107293346A CN201710425876.4A CN201710425876A CN107293346A CN 107293346 A CN107293346 A CN 107293346A CN 201710425876 A CN201710425876 A CN 201710425876A CN 107293346 A CN107293346 A CN 107293346A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G4/00—Radioactive sources
- G21G4/04—Radioactive sources other than neutron sources
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G4/00—Radioactive sources
- G21G4/04—Radioactive sources other than neutron sources
- G21G4/06—Radioactive sources other than neutron sources characterised by constructional features
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Abstract
The invention discloses a kind of Sn 113/In 113m generators and preparation method, preparation method includes：1) to stannic chloride [113Sn] in the aqueous solution, the bromine aqueous solution is added, adjust radioactive concentration with aqueous acid；2) support frame is set in lead protection tank, support frame is connected with heating plate；Heating plate is connected with attaching plug；3) nano oxidized particulate zirconia is put into glass splitter, by step 1) liquid that obtains, added from feed tube, then eluted with sodium-chloride water solution, after elution, will be equipped with absorption tin [113Sn] nano oxidized particulate zirconia glass splitter load step 2) obtain device in, heating plate is contacted with the outer surface in the middle part of glass splitter.The present invention has elution efficiency high, and leakage wears that rate is low, and elution volume is small；Elute speed fast, staff can be made to shorten the operating time as far as possible, reduction is by irradiation risk.
Description
Technical field
The present invention relates to the preparation method of a kind of medical or industrial radionuclide generator, more specifically to
A kind of preparation method of Sn-113/In-113m generators.
Background technology
Radionuclide generator is called cow, different in the distribution of adsorbent from daughter nuclide using parent nuclide, leads to
Cross relatively long half-life parent radionuclide and prepare device compared with short-half-life daughter radionuclide, with leacheate constantly from
Radionuclide generator elutes the radionuclide needed for medical or commercial Application, the radionuclide widely applied at present
Have molybdenum [99Mo]/technetium [99mTc] generator, tin [113Sn]/indium [113mIn] generator and strontium [90Sr]/yttrium [90Y] generator etc..Put
Penetrating property nucleic indium [113mIn] there is good chemical and nulcear properties, half-life period is 99.8min, and gamma energy is 391keV, is wide
Generally applied to clinical medicine or the critical nuclide of industrial spike application, radionuclide indium [113mIn] prepared with compound
Different radiopharmaceutical or radioactively labelled substance, for clinical nuclear medicine imaging, such as thyroid gland, brain, liver,spleen,kidney, lung, bone
Diagnosis or industrial spike application, such as oil reservoir logging with marrow, thrombus, injury of blood vessel, inflammation etc., dose of radiation is small, poison
Property small and effect on environment it is small.Due to radionuclide indium [113mIn] half-life period is very short, it is difficult to meet the doctor away from reactor
Institute, therefore tin [113Sn]/indium [113mIn] generator provide clinical practice or commercial Application radionuclide indium [113mIn] weight
Originate, it is easy to use.
Will113mIn nucleic is from mother and sons' body113Sn/113mSeparated in In mixtures, there are a variety of chemical methodes, such as hydration oxygen
Change zirconium post separation method, alumina column partition method, Anion exchange resin separation and solvent extraction etc..These Chemical Decomposition method energy
113mIn nucleic is from mother and sons' body113Sn/113mSeparated in In mixtures, but be due to absorption of the separatory release agent to tin
Finite capacity is either cumbersome.Such as Chinese patent CN86105863 discloses one kind and " prepares the change of indium -113m generators
Learn processing method ".The preparation method be by after irradiation tin [113Sn] add hydrochloric acid in target, and logical chlorine conversion into113SnCl4
Afterwards, appropriate ZrOCl is added2Solution is mixed, and mixed liquor is added dropwise concentrated ammonia liquor and formed under agitation113SnO2-ZrO2Colloid mixture (pH
4.0) precipitate, colloid mixture precipitation is poured into sintered glass funnel, vacuum pump pressure suction filtration, 100-120 DEG C of drying, mechanical grinding
It is broken into unbodied113SnO2-ZrO2Colloidal solid, what is be made113SnO2-ZrO2Colloidal solid is transferred to has been charged into screen in advance
Cover in the small exchange column in lead set and Sn-113/In-113m generators are made.It this method solve in disclosed separation method
The problem of release agent is low to the adsorption capacity of tin, but the cumbersome works such as suction filtration, high temperature drying, machinery grinding are needed in preparation process
Skill, operation difficulty is high, and operating time length, operating personnel it is big by irradiation dose.
The content of the invention
The purpose of the present invention overcomes the deficiencies in the prior art low, easy to operate, easily-controllable, easy there is provided a kind of cost
A kind of Sn-113/In-113m generators.
Second object of the present invention is to provide a kind of preparation method of Sn-113/In-113m generators.
Technical scheme is summarized as follows：
A kind of preparation method of Sn-113/In-113m generators, comprises the following steps：
1) in a reservoir, it is put into the stannic chloride that pH=0.5-2,0.1-3mL radioactive concentration are 1.85-3.7GBq/mL
[113Sn] aqueous solution, add 1-6mL, 1-6M aqueous acid, add 0.5-2.5mL mass concentrations 99% the bromine aqueous solution or
The aqueous sodium hypochlorite solution of mass concentration 10%, then it is 185-370MBq/mL to be adjusted with 1-6M aqueous acid to radioactive concentration；
2) support frame (9) is set in lead protection tank (7), support frame is connected with heating plate (4)；Heating plate (4) and electricity
Source plug (5) is connected；
3) glass splitter (3) is taken, sieve plate (1) is set in glass separation column bottom, glass fiber is put on sieve plate 1, then
The nano oxidized particulate zirconias of 5-6g (8) are put into, one end of feed tube (2) is arranged on to the top of the glass splitter, drain pipe
(6) one end is arranged on the bottom of glass splitter, by step 1) liquid that obtains, with 0.5-1mL/min flow velocity from feed liquor
Manage (2) to add, then eluted with pH=0.5-2 mass concentration for 0.9% sodium-chloride water solution, after elution, obtain being equipped with and inhale
Attached tin [113Sn] nano oxidized particulate zirconia glass splitter, will it is described equipped with absorption tin [113Sn] nano oxidized particulate zirconia
Glass splitter load step 2) obtain device in, heating plate (4) is contacted with the outer surface in the middle part of glass splitter, obtained
To Sn-113/In-113m generators.
Acid is preferably hydrochloric acid, sulfuric acid or nitric acid.
The particle diameter of nano oxidized particulate zirconia is preferably 10-20nm.
The diameter of glass splitter is preferably 5mm-15mm, and the length of the glass splitter is preferably 80-150mm.
Sn-113/In-113m generators prepared by the above method.
Advantages of the present invention：
1. the Sn-113/In-113m generators of the present invention have elution efficiency high, leakage wears that rate is low, and elution volume is small；Elution
Speed is fast, staff can be made to shorten the operating time as far as possible, and reduction is by irradiation risk.
2. using bromine or sodium hypochlorite for oxidant, its strong oxidizing property can ensure Sn2+It is oxidized complete, raising nanometer
The adsorption efficiency of zirconium oxide.
3. chemical reagent used in the method for the present invention is conventional commercial reagent, buying is convenient, cheap, production
Cost is low.
4. setting polyimides heating plate in the lead protection tank for transporting the generator is preserved, heating plate leads to 12V direct currents
I.e. heatable, the liquid that will can have been frozen in energization 20-25min in splitter all thawings make it in the Northern Part of China winter
Using more facilitating under season low temperature condition, clinical nuclear medicine inspection and industrial oil field spike can be applied to simultaneously.
Brief description of the drawings
Fig. 1 is the structural representation of the Sn-113/In-113m generators of the present invention.
Fig. 2 is Sn-113/In-113m generator elution curves prepared by embodiment 1.
Embodiment
With reference to specific implementation, the present invention is further illustrated.The chemical reagent used in all embodiments is equal
It is pure to analyze.
Embodiment 1
A kind of preparation method of Sn-113/In-113m generators, comprises the following steps：
1) in a reservoir, be put into pH=1, volume be 0.5mL radioactive concentrations be 2GBq/mL stannic chloride [113Sn] it is water-soluble
Liquid, adds 5mL, 3M aqueous hydrochloric acid solution, adds the bromine aqueous solution of 2mL mass concentrations 99%, then with 5M aqueous hydrochloric acid solution
Regulation to radioactive concentration is 185MBq/mL；
2) support frame 9 is set in lead protection tank 7, support frame is connected with heating plate 4；Heating plate 4 connects with attaching plug 5
Connect；
3) a diameter of 9mm is taken, length is 100mm glass splitter, sieve plate 1 is set in glass separation column bottom, in sieve
The thick glass fibers of 1mm are put on plate 1, the nano oxidized particulate zirconias 8 of 5g are placed into, the particle diameter of nano oxidized particulate zirconia is 10nm, side
Feed side vibration, one end of feed tube 2 is arranged on to the top of the glass splitter, one end of drain pipe 6 is arranged on glass
The bottom of splitter, by step 1) liquid that obtains, added with 0.5mL/min flow velocity from feed tube 2, then with pH=1.5's
Mass concentration for 0.9% sodium-chloride water solution elute, after elution, obtain equipped with absorption tin [113Sn] nano oxidized particulate zirconia
Glass splitter, will it is described equipped with absorption tin [113Sn] nano oxidized particulate zirconia glass splitter load step 2) obtain
Device in, heating plate 4 is contacted with the outer surface in the middle part of glass splitter, Sn-113/In-113m generators are obtained.
Input tin [113Sn] solution radioactive activity be 1GBq, initial leacheate tin [113Sn] radioactive activity is
37MBq, adsorption efficiency be 96.3% (adsorption efficiency=(input tin [113Sn] radioactive activity-leacheate tin [113Sn] radiation
Property activity) ÷ input tin [113Sn] radioactive activity × 100%), elution curve is as shown in Figure 2.
In the leacheate of acquisition113mIn In daughters,113Sn/113mIn ＜ 0.1%,113mIn radioactive concentrations 4.0 × 108Bq/
ML,113mIn radionuclide purities are more than 99%, and radiochemical purity is more than 96%.Generator113Rate ＜ is worn in Sn leakages
0.05%, elution efficiency is more than 80% (after generator balance, after elution efficiency=elution in leacheate113mIn radioactivity is total
Count before activity/elution in generator113mIn radioactivity total activity × 100%).
Embodiment 2
A kind of preparation method of Sn-113/In-113m generators, comprises the following steps：
1) in a reservoir, add pH=0.5, volume be 1mL radioactive concentrations be 1.85GBq/mL stannic chloride [113Sn]
The aqueous solution, adds 1mL, 6M aqueous sulfuric acid, adds the bromine aqueous solution of 1.5mL mass concentrations 99%, then with 1M sulfuric acid
It is 185MBq/mL that the aqueous solution, which is adjusted to radioactive concentration,；
2) support frame 9 is set in lead protection tank 7, support frame is connected with heating plate 4；Heating plate 4 connects with attaching plug 5
Connect；
3) a diameter of 6mm is taken, length is 140mm glass splitter, sieve plate 1 is set in glass separation column bottom, in sieve
The thick glass fibers of 1mm are put on plate 1, the nano oxidized particulate zirconias of 6g are placed into, the particle diameter of nano oxidized particulate zirconia is 20nm, Bian Jia
Expect side vibration, one end of feed tube 2 is arranged on to the top of the glass splitter, one end of drain pipe 6 is arranged on glass point
From the bottom of post, by step 1) liquid that obtains, added with 0.5mL/min flow velocity from feed tube 2, then with pH=0.5 matter
Measure concentration for 0.9% sodium-chloride water solution elute, after elution, obtain equipped with absorption tin [113Sn] nano oxidized particulate zirconia
Glass splitter, will it is described equipped with absorption tin [113Sn] nano oxidized particulate zirconia glass splitter load step 2) obtain
In device, heating plate 4 is contacted with the outer surface in the middle part of glass splitter, Sn-113/In-113m generators are obtained.
Input tin [113Sn] radioactive activity be 1.85GBq, initial leacheate tin [113Sn] radioactive activity is
33.3MBq.It is respectively 98.2% and 85% to calculate adsorption efficiency, elution efficiency by the method for embodiment 1.
In the leacheate of acquisition113mIn In daughters,113Sn ＜ 0.1%,113mIn radionuclide purities are more than 99%, radiation
Chemical purity is more than 96%.Generator113Rate ＜ 0.05% is worn in Sn leakages.
Embodiment 3
A kind of preparation method of Sn-113/In-113m generators, comprises the following steps：
1) in a reservoir, be put into pH=2, volume be 1mL radioactive concentrations be 3.7GBq/mL stannic chloride [113Sn] it is water-soluble
Liquid, adds 6mL, 1M aqueous solution of nitric acid, adds the bromine aqueous solution of 2.5mL mass concentrations 99%, then water-soluble with 1M nitric acid
It is 370MBq/mL that liquid, which is adjusted to radioactive concentration,；
2) support frame 9 is set in lead protection tank 7, support frame is connected with heating plate 4；Heating plate 4 connects with attaching plug 5
Connect；
3) a diameter of 9mm is taken, length is 100mm glass splitter, sieve plate 1 is set in glass separation column bottom, in sieve
The thick glass fibers of 1mm are put on plate 1, the nano oxidized particulate zirconias of 5g are placed into, the particle diameter of nano oxidized particulate zirconia is 10nm, Bian Jia
Expect side vibration, one end of feed tube 2 is arranged on to the top of the glass splitter, one end of drain pipe 6 is arranged on glass point
From the bottom of post, by step 1) liquid that obtains, added with 0.5mL/min flow velocity from feed tube 2, then with pH=1.5 matter
Measure concentration for 0.9% sodium-chloride water solution elute, after elution, obtain equipped with absorption tin [113Sn] nano oxidized particulate zirconia
Glass splitter, will it is described equipped with absorption tin [113Sn] nano oxidized particulate zirconia glass splitter load step 2) obtain
In device, heating plate 4 is contacted with the outer surface in the middle part of glass splitter, Sn-113/In-113m generators are obtained.
Input tin [113Sn] radioactive activity be 3.7GBq, initial leacheate tin [113Sn] radioactive activity is
55.6MBq.It is respectively 98.5% and 83% to calculate adsorption efficiency, elution efficiency by the method for embodiment 1.
In the leacheate of acquisition113mIn In daughters,113Sn ＜ 0.1%,113mIn radionuclide purities are more than 99%, radiation
Chemical purity is more than 96%.Generator113Rate ＜ 0.05% is worn in Sn leakages.
Embodiment 4
A kind of preparation method of Sn-113/In-113m generators, comprises the following steps：
1) in a reservoir, be put into pH=1.5,0.1mL radioactive concentration be 3.7GBq/mL stannic chloride [113Sn] it is water-soluble
Liquid, adds 3mL, 3M aqueous solution of nitric acid, adds the bromine aqueous solution of 0.5mL mass concentrations 99%, then water-soluble with 6M nitric acid
It is 200MBq/mL that liquid, which is adjusted to radioactive concentration,；
2) support frame 9 is set in lead protection tank 7, support frame is connected with heating plate 4；Heating plate 4 connects with attaching plug 5
Connect；
3) a diameter of 9mm is taken, length is 102mm glass splitter, sieve plate 1 is set in glass separation column bottom, in sieve
The thick glass fibers of 1mm are put on plate 1, the nano oxidized particulate zirconias of 5g are placed into, the particle diameter of nano oxidized particulate zirconia adds for 20nm sides
Expect side vibration, one end of feed tube 2 is arranged on to the top of the glass splitter, one end of drain pipe 6 is arranged on glass point
From the bottom of post, by step 1) liquid that obtains, added with 0.5mL/min flow velocity from feed tube 2, then with pH=1.5 matter
Measure concentration for 0.9% sodium-chloride water solution elute, after elution, obtain equipped with absorption tin [113Sn] nano oxidized particulate zirconia
Glass splitter, will it is described equipped with absorption tin [113Sn] nano oxidized particulate zirconia glass splitter load step 2) obtain
In device, heating plate 4 is contacted with the outer surface in the middle part of glass splitter, Sn-113/In-113m generators are obtained.
Input tin [113Sn] radioactive activity be 0.37GBq, initial leacheate tin [113Sn] radioactive activity is
9.6MBq.It is respectively 97.4% and 82% to calculate adsorption efficiency, elution efficiency by the method for embodiment 1.
In the leacheate of acquisition113mIn In daughters,113Sn ＜ 0.1%,113mIn radionuclide purities are more than 99%, radiation
Chemical purity is more than 96%.Generator113Rate ＜ 0.05% is worn in Sn leakages.
Embodiment 5
A kind of preparation method of Sn-113/In-113m generators, comprises the following steps：
1) in a reservoir, add pH=1.0,2mL radioactive concentration for 2.22GBq/mL stannic chloride [113Sn] aqueous solution,
3mL, 3M aqueous sulfuric acid are added, the bromine aqueous solution of 0.5mL mass concentrations 99% is added, then adjusted with 6M aqueous sulfuric acid
Section to radioactive concentration is 220MBq/mL；
2) support frame 9 is set in lead protection tank 7, support frame is connected with heating plate 4；Heating plate 4 connects with attaching plug 5
Connect；
3) a diameter of 5mm is taken, length is 150mm glass splitter, sieve plate 1 is set in glass separation column bottom, in sieve
The thick glass fibers of 1mm are put on plate 1, the nano oxidized particulate zirconias of 5g are placed into, the particle diameter of nano oxidized particulate zirconia is 20nm, Bian Jia
Expect side vibration, one end of feed tube 2 is arranged on to the top of the glass splitter, one end of drain pipe 6 is arranged on glass point
From the bottom of post, by step 1) liquid that obtains, added with 0.5mL/min flow velocity from feed tube (2), then with pH=1.5's
Mass concentration for 0.9% sodium-chloride water solution elute, after elution, obtain equipped with absorption tin [113Sn] nano oxidized particulate zirconia
Glass splitter, will it is described equipped with absorption tin [113Sn] nano oxidized particulate zirconia glass splitter load step 2) obtain
Device in, heating plate 4 is contacted with the outer surface in the middle part of glass splitter, Sn-113/In-113m generators are obtained.
Input tin [113Sn] radioactive activity be 4.44GBq, initial leacheate tin [113Sn] radioactive activity is
56.7MBq.It is respectively 98.7% and 82% to calculate adsorption efficiency, elution efficiency by the method for embodiment 1.
In the leacheate of acquisition113mIn In daughters,113Sn ＜ 0.1%,113mIn radionuclide purities are more than 99%, radiation
Chemical purity is more than 96%.Generator113Rate ＜ 0.05% is worn in Sn leakages.
Embodiment 6
A kind of preparation method of Sn-113/In-113m generators, comprises the following steps：
1) in a reservoir, be put into pH=1,3mL radioactive concentration be 1.85GBq/mL stannic chloride [113Sn] aqueous solution, plus
Enter 3mL, 1M aqueous hydrochloric acid solution, add the aqueous sodium hypochlorite solution of 2.5mL mass concentrations 10%, then adjusted with 1M aqueous hydrochloric acid solution
Section to radioactive concentration is 185MBq/mL；
2) support frame 9 is set in lead protection tank 7, support frame is connected with heating plate 4；Heating plate 4 connects with attaching plug 5
Connect；
3) a diameter of 15mm is taken, length is 80mm glass splitter, sieve plate 1 is set in glass separation column bottom, in sieve
The thick glass fibers of 1mm are put on plate 1, the nano oxidized particulate zirconias of 6g are placed into, the particle diameter of nano oxidized particulate zirconia is 20nm, Bian Jia
Expect side vibration, one end of feed tube 2 is arranged on to the top of the glass splitter, one end of drain pipe 6 is arranged on glass point
From the bottom of post, by step 1) liquid that obtains, added with 1mL/min flow velocity from feed tube 2, then dense with pH=2 quality
Spend for 0.9% sodium-chloride water solution elution, after elution, obtain equipped with absorption tin [113Sn] nano oxidized particulate zirconia glass
Splitter, will it is described equipped with absorption tin [113Sn] nano oxidized particulate zirconia glass splitter load step 2) obtain device
It is interior, heating plate (4) is contacted with the outer surface in the middle part of glass splitter, Sn-113/In-113m generators are obtained.
Input tin [113Sn] radioactive activity be 5.55GBq, initial leacheate tin [113Sn] radioactive activity is
72.2MBq.It is respectively 98.7% and 82% to calculate adsorption efficiency, elution efficiency by the method for embodiment 1.
In the leacheate of acquisition113mIn In daughters,113Sn ＜ 0.1%,113mIn radionuclide purities are more than 99%, radiation
Chemical purity is more than 96%.Generator113Rate ＜ 0.05% is worn in Sn leakages.
Claims (5)
1. a kind of preparation method of Sn-113/In-113m generators, it is characterized in that comprising the following steps：
1) in a reservoir, be put into pH=0.5-2,0.1-3mL radioactive concentration be 1.85-3.7GBq/mL stannic chloride [113Sn]
The aqueous solution, adds 1-6mL, 1-6M aqueous acid, and the bromine aqueous solution or quality for adding 0.5-2.5mL mass concentrations 99% are dense
10% aqueous sodium hypochlorite solution is spent, then it is 185-370MBq/mL to be adjusted with 1-6M aqueous acid to radioactive concentration；
2) support frame (9) is set in lead protection tank (7), support frame is connected with heating plate (4)；Heating plate (4) is inserted with power supply
Head (5) connection；
3) glass splitter (3) is taken, sieve plate (1) is set in glass separation column bottom, glass fiber is put on sieve plate 1, places into
The nano oxidized particulate zirconias of 5-6g (8), one end of feed tube (2) are arranged on the top of the glass splitter, drain pipe (6)
One end is arranged on the bottom of glass splitter, by step 1) liquid that obtains, with 0.5-1mL/min flow velocity from feed tube (2)
Add, then eluted with pH=0.5-2 mass concentration for 0.9% sodium-chloride water solution, after elution, obtained equipped with absorption tin
[113Sn] nano oxidized particulate zirconia glass splitter, will it is described equipped with absorption tin [113Sn] nano oxidized particulate zirconia glass
Glass splitter load step 2) obtain device in, heating plate (4) is contacted with the outer surface in the middle part of glass splitter, obtained
Sn-113/In-113m generators.
2. according to the method described in claim 1, it is characterized in that the acid is hydrochloric acid, sulfuric acid or nitric acid.
3. according to the method described in claim 1, it is characterised in that the particle diameter of the nano oxidized particulate zirconia is 10-20nm.
4. according to the method described in claim 1, it is characterised in that a diameter of 5mm-15mm of the glass splitter, the glass
The length of glass splitter is 80-150mm.
5. claim 1-5 method prepare Sn-113/In-113m generators.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710425876.4A CN107293346A (en) | 2017-06-08 | 2017-06-08 | A kind of Sn 113/In 113m generators and preparation method |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710425876.4A CN107293346A (en) | 2017-06-08 | 2017-06-08 | A kind of Sn 113/In 113m generators and preparation method |
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| CN107293346A true CN107293346A (en) | 2017-10-24 |
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ID=60097089
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| Application Number | Title | Priority Date | Filing Date |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114999701A (en) * | 2022-05-31 | 2022-09-02 | 中国核动力研究设计院 | Strontium [ 2 ] 90 Sr]-yttrium [ alpha ], [ alpha ] and [ alpha ] or 90 Y]Generator and separation method |
| WO2024139881A1 (en) * | 2022-12-29 | 2024-07-04 | 中国核动力研究设计院 | Generator for radionuclide separation and extraction, operation method therefor and use thereof |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3450597A (en) * | 1966-12-23 | 1969-06-17 | Union Carbide Corp | Production of high purity radioactive indium-113m |
| US3561932A (en) * | 1967-01-26 | 1971-02-09 | New England Nuclear Corp | Indium generator |
| CN86105863A (en) * | 1986-09-05 | 1988-03-16 | 核工业部第一研究设计院 | The chemical treatment method of preparation indium-113m generator |
| RU2073928C1 (en) * | 1994-05-11 | 1997-02-20 | Физико-энергетический институт | Method of preparing indium-113m generator |
-
2017
- 2017-06-08 CN CN201710425876.4A patent/CN107293346A/en active Pending
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3450597A (en) * | 1966-12-23 | 1969-06-17 | Union Carbide Corp | Production of high purity radioactive indium-113m |
| GB1215354A (en) * | 1966-12-23 | 1970-12-09 | Union Carbide Corp | PRODUCTION OF HIGH PURITY RADIOACTIVE INDIUM-113m |
| US3561932A (en) * | 1967-01-26 | 1971-02-09 | New England Nuclear Corp | Indium generator |
| CN86105863A (en) * | 1986-09-05 | 1988-03-16 | 核工业部第一研究设计院 | The chemical treatment method of preparation indium-113m generator |
| RU2073928C1 (en) * | 1994-05-11 | 1997-02-20 | Физико-энергетический институт | Method of preparing indium-113m generator |
Non-Patent Citations (2)
| Title |
|---|
| G. SUBRAMANIAN AND J. G. MCAFEE: "《A Radioisotope Generator of Indium-1 13m》", 《INTERNATIONAL JOURNAL OF APPLIED RADIATION AND ISOTOPES》 * |
| K. TERANISHI ET AL.: "113Sn–113mIn generator with a glass beads column", 《JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY》 * |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114999701A (en) * | 2022-05-31 | 2022-09-02 | 中国核动力研究设计院 | Strontium [ 2 ] 90 Sr]-yttrium [ alpha ], [ alpha ] and [ alpha ] or 90 Y]Generator and separation method |
| WO2024139881A1 (en) * | 2022-12-29 | 2024-07-04 | 中国核动力研究设计院 | Generator for radionuclide separation and extraction, operation method therefor and use thereof |
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Application publication date: 20171024 |