CN116646104A - Separation and preparation from waste Sr-90 radioactive source 90 Method of Y nuclides - Google Patents
Separation and preparation from waste Sr-90 radioactive source 90 Method of Y nuclides Download PDFInfo
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- CN116646104A CN116646104A CN202310421155.1A CN202310421155A CN116646104A CN 116646104 A CN116646104 A CN 116646104A CN 202310421155 A CN202310421155 A CN 202310421155A CN 116646104 A CN116646104 A CN 116646104A
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- 238000000034 method Methods 0.000 title claims abstract description 58
- CIOAGBVUUVVLOB-NJFSPNSNSA-N Strontium-90 Chemical compound [90Sr] CIOAGBVUUVVLOB-NJFSPNSNSA-N 0.000 title claims abstract description 36
- 239000002699 waste material Substances 0.000 title claims abstract description 27
- 230000002285 radioactive effect Effects 0.000 title claims abstract description 21
- 238000000926 separation method Methods 0.000 title claims abstract description 18
- 238000002360 preparation method Methods 0.000 title claims description 11
- 238000002386 leaching Methods 0.000 claims abstract description 26
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 claims abstract description 21
- 230000008569 process Effects 0.000 claims abstract description 19
- 238000001914 filtration Methods 0.000 claims abstract description 13
- 238000010438 heat treatment Methods 0.000 claims abstract description 12
- 229910052742 iron Inorganic materials 0.000 claims abstract description 10
- 238000006243 chemical reaction Methods 0.000 claims abstract description 9
- 239000007788 liquid Substances 0.000 claims abstract description 7
- 230000001105 regulatory effect Effects 0.000 claims abstract description 7
- QZPSXPBJTPJTSZ-UHFFFAOYSA-N aqua regia Chemical compound Cl.O[N+]([O-])=O QZPSXPBJTPJTSZ-UHFFFAOYSA-N 0.000 claims abstract description 6
- 239000002253 acid Substances 0.000 claims description 10
- 230000005855 radiation Effects 0.000 claims description 9
- 239000002244 precipitate Substances 0.000 claims description 7
- QGZKDVFQNNGYKY-UHFFFAOYSA-N Ammonia Chemical compound N QGZKDVFQNNGYKY-UHFFFAOYSA-N 0.000 claims description 4
- CDBYLPFSWZWCQE-UHFFFAOYSA-L Sodium Carbonate Chemical compound [Na+].[Na+].[O-]C([O-])=O CDBYLPFSWZWCQE-UHFFFAOYSA-L 0.000 claims description 4
- BWHMMNNQKKPAPP-UHFFFAOYSA-L potassium carbonate Chemical compound [K+].[K+].[O-]C([O-])=O BWHMMNNQKKPAPP-UHFFFAOYSA-L 0.000 claims description 4
- 239000012528 membrane Substances 0.000 claims description 3
- 238000004663 powder metallurgy Methods 0.000 claims description 3
- UIIMBOGNXHQVGW-DEQYMQKBSA-M Sodium bicarbonate-14C Chemical compound [Na+].O[14C]([O-])=O UIIMBOGNXHQVGW-DEQYMQKBSA-M 0.000 claims description 2
- 150000008044 alkali metal hydroxides Chemical class 0.000 claims description 2
- 229910021529 ammonia Inorganic materials 0.000 claims description 2
- 238000005119 centrifugation Methods 0.000 claims description 2
- 238000004519 manufacturing process Methods 0.000 claims description 2
- 229910000028 potassium bicarbonate Inorganic materials 0.000 claims description 2
- 235000015497 potassium bicarbonate Nutrition 0.000 claims description 2
- 239000011736 potassium bicarbonate Substances 0.000 claims description 2
- 229910000027 potassium carbonate Inorganic materials 0.000 claims description 2
- 235000011181 potassium carbonates Nutrition 0.000 claims description 2
- TYJJADVDDVDEDZ-UHFFFAOYSA-M potassium hydrogencarbonate Chemical compound [K+].OC([O-])=O TYJJADVDDVDEDZ-UHFFFAOYSA-M 0.000 claims description 2
- 229910000029 sodium carbonate Inorganic materials 0.000 claims description 2
- 235000017550 sodium carbonate Nutrition 0.000 claims description 2
- 239000002994 raw material Substances 0.000 abstract description 11
- 238000001556 precipitation Methods 0.000 abstract description 8
- 239000012535 impurity Substances 0.000 abstract description 6
- 239000002901 radioactive waste Substances 0.000 abstract description 4
- 238000004064 recycling Methods 0.000 abstract description 2
- 239000000243 solution Substances 0.000 description 30
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 description 15
- VEXZGXHMUGYJMC-UHFFFAOYSA-N Hydrochloric acid Chemical compound Cl VEXZGXHMUGYJMC-UHFFFAOYSA-N 0.000 description 5
- 150000002500 ions Chemical class 0.000 description 5
- 230000007547 defect Effects 0.000 description 4
- 239000003513 alkali Substances 0.000 description 3
- 238000006386 neutralization reaction Methods 0.000 description 3
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 2
- 239000004480 active ingredient Substances 0.000 description 2
- 239000006227 byproduct Substances 0.000 description 2
- 238000004587 chromatography analysis Methods 0.000 description 2
- 230000000052 comparative effect Effects 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000002474 experimental method Methods 0.000 description 2
- 239000010931 gold Substances 0.000 description 2
- -1 iron ions Chemical class 0.000 description 2
- 230000003472 neutralizing effect Effects 0.000 description 2
- 229910017604 nitric acid Inorganic materials 0.000 description 2
- 230000001590 oxidative effect Effects 0.000 description 2
- 239000011347 resin Substances 0.000 description 2
- 229920005989 resin Polymers 0.000 description 2
- 238000000638 solvent extraction Methods 0.000 description 2
- 238000001179 sorption measurement Methods 0.000 description 2
- 206010005949 Bone cancer Diseases 0.000 description 1
- 208000018084 Bone neoplasm Diseases 0.000 description 1
- 229930182555 Penicillin Natural products 0.000 description 1
- JGSARLDLIJGVTE-MBNYWOFBSA-N Penicillin G Chemical compound N([C@H]1[C@H]2SC([C@@H](N2C1=O)C(O)=O)(C)C)C(=O)CC1=CC=CC=C1 JGSARLDLIJGVTE-MBNYWOFBSA-N 0.000 description 1
- 239000000443 aerosol Substances 0.000 description 1
- 238000013459 approach Methods 0.000 description 1
- 238000003556 assay Methods 0.000 description 1
- 239000003153 chemical reaction reagent Substances 0.000 description 1
- 238000004140 cleaning Methods 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 239000008367 deionised water Substances 0.000 description 1
- 229910021641 deionized water Inorganic materials 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 238000009792 diffusion process Methods 0.000 description 1
- 238000004090 dissolution Methods 0.000 description 1
- 239000003814 drug Substances 0.000 description 1
- 239000012467 final product Substances 0.000 description 1
- PCHJSUWPFVWCPO-UHFFFAOYSA-N gold Chemical compound [Au] PCHJSUWPFVWCPO-UHFFFAOYSA-N 0.000 description 1
- 229910052737 gold Inorganic materials 0.000 description 1
- PQTCMBYFWMFIGM-UHFFFAOYSA-N gold silver Chemical compound [Ag].[Au] PQTCMBYFWMFIGM-UHFFFAOYSA-N 0.000 description 1
- 201000007270 liver cancer Diseases 0.000 description 1
- 208000014018 liver neoplasm Diseases 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 239000012982 microporous membrane Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000005457 optimization Methods 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 229940049954 penicillin Drugs 0.000 description 1
- 239000000047 product Substances 0.000 description 1
- 238000003904 radioactive pollution Methods 0.000 description 1
- 230000035484 reaction time Effects 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
- 238000005070 sampling Methods 0.000 description 1
- 239000011734 sodium Substances 0.000 description 1
- 229910001415 sodium ion Inorganic materials 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
- 239000011550 stock solution Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
- 230000008685 targeting Effects 0.000 description 1
- 230000001225 therapeutic effect Effects 0.000 description 1
- 238000005406 washing Methods 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Chemical compound O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/007—Recovery of isotopes from radioactive waste, e.g. fission products
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
- Y02P10/00—Technologies related to metal processing
- Y02P10/20—Recycling
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Manufacture And Refinement Of Metals (AREA)
Abstract
The present invention relates to 90 The technical field of Y nuclide separation, in particular to a method for separating and preparing from waste Sr-90 radioactive source 90 A method of Y species. The method comprises a pretreatment process and a separation process, wherein the pretreatment process sequentially comprises the following steps: 1) In waste Sr-90 radioactive sources 90 Leaching Sr by using aqua regia to obtain leaching liquid; 2) Heating the leachate to remove NO therefrom 2 The method comprises the steps of carrying out a first treatment on the surface of the 3) Adding iron into the leaching solution for reaction; 4) Regulating the pH of the leaching solution to 12-14, and filtering or centrifuging to obtain clear liquid; 5) Regulating pH of the clear solution to 4-7, standing for more than 14 days to obtain 90 Sr/ 90 And Y solution. The invention takes waste Sr-90 radioactive source as raw material, and obtains the needed Sr-90 raw material after dissolving and removing impurities, thereby being used for recycling and producing radioactive waste 90 The Y nuclide provides a new method, and the purity of the Y nuclide can be separated to be more than 99.8% by adopting a simple precipitation method 90 A Y species.
Description
Technical Field
The present invention relates to 90 The technical field of Y nuclide separation, in particular to a method for separating and preparing from waste Sr-90 radioactive source 90 A method of Y species.
Background
90 The Y nuclide is a pure beta nuclide, T 1/2 =64 h, maximum energy of emitted β -particles 2.28MeV, decay daughter 90 Zr。 90 The Y nuclide has good chelating property, is a valuable therapeutic radioactive isotope, and the prepared radioactive medicament has wide application prospect in the medical aspects of treating liver cancer, bone cancer and the like, and can also be used for preparing markers and tracers.
90 The preparation of Y nuclides is of two general types, one is by (n, gamma) or (g, p) nuclear reactions, using neutron radiation (e.g. in a reactor) 89 Y or accelerator targeting 91 Zr generation 90 Y nuclides, the reaction conditions of such processes are very demanding. Another type of method is from 90 Sr/ 90 Y decay equilibrium separation 90 The Y nuclide is simple to operate, and common methods include a resin adsorption method, a solvent extraction method, a chromatography method, a precipitation method and the like.
The precipitation method is to use Y (OH) 3 And Sr (OH) 2 Is different in solubility product Ksp, Y (OH) 3 Can be precipitated under low pH condition, and filtered 90 Y nuclide slave 90 Sr/ 90 Separation of the Y-balance, e.g. Rubel Chakravarty et al, from clinical pharmaceutical grade under alkaline conditions using two-step radiochemistry 90 A Y species.
At present, a mother nucleus is commonly obtained 90 The Sr source is spent fuel and the like, and the raw material cost is higher. In view of this, the present invention has been made.
Disclosure of Invention
The invention overcomes the defects existing in the prior art and provides a method for separating and preparing the waste Sr-90 radioactive source 90 The method of Y nuclide realizes the reutilization of Sr-90 radioactive waste, and is developed and produced 90 The Y species provides a new approach.
In order to achieve the above purpose, the invention adopts the following technical scheme:
separation and preparation from waste Sr-90 radioactive source 90 The method for preparing the Y nuclide comprises a pretreatment process and a separation process, wherein the pretreatment process sequentially comprises the following steps:
1) In waste Sr-90 radioactive sources 90 Leaching Sr by using aqua regia to obtain leaching liquid;
2) Heating the leachate to remove NO therefrom 2 ；
3) Adding iron into the leaching solution for reaction;
4) Regulating the pH of the leaching solution to 12-14, and filtering or centrifuging to obtain clear liquid;
5) Regulating pH of the clear solution to 4-7, standing for more than 14 days to obtain 90 Sr/ 90 And Y solution.
In particular, the adoption of aqua regia can improve the waste Sr-90 radioactive source 90 Leaching rate of Sr; NO (NO) 2 Affecting the subsequent reduction of chloroauric acid, also increasing subsequent iron or alkali consumption, and direct neutralization with alkali also increases byproducts such as Na + Ion, etc. by heating the leaching solution to remove NO 2 Byproducts of subsequent reactions can be reduced; adding iron into the leaching solution to react, neutralizing acid, removing introduced iron ions in subsequent precipitation, and introducing Na such as NaOH + The ions cannot be removed, and the strong oxidizing substances such as chloroauric acid generated in the process of leaching aqua regia can be reduced; adjusting pH of the leachate to 12-14, filtering or centrifuging to remove impurity ion such as Fe 2+ (Fe 3+ )、Au + 、Ag + Ions, while the balance of the leachate is maintained 90 The Y nuclides are also filtered out; regulating pH of the clear solution to 4-7, standing for more than 14 days to obtain the final product 90 Sr and 90 y reaches equilibrium again and is thus used as a raw material for the next separation step.
The pretreatment process of the invention 90 Sr/ 90 The Y solution may be prepared using any known method 90 Sr/ 90 Y decay equilibrium separation 90 Method for carrying out Y nuclideSubsequent separation procedures (e.g., resin adsorption, solvent extraction, chromatography, precipitation).
Preferably, the waste Sr-90 radiation source is a source sheet of a waste strontium-90 applicator prepared by a powder metallurgy process. The waste strontium-90 applicator source sheet is a primary waste Sr-90 radiation source produced by powder metallurgy processes, primarily gold silver, wherein 90 The Sr active ingredient is mainly below a gold layer of a few microns, the method is particularly suitable for waste strontium-90 applicator source tablets, and most of the Sr active ingredient can be leached out by aqua regia 90 The Sr nuclide dissolves out.
Further preferably, the leaching temperature in the step 1) is room temperature, and the leaching time is 1-4h. The present invention has found that either the temperature is too low or the leaching time is too short, in the spent strontium-90 applicator source sheet 90 The leaching effect of Sr nuclides is obviously reduced, radioactive aerosol is easy to volatilize when the temperature is too high, the defect of radioactive pollution diffusion is caused, and the defect of excessive dissolution of Ag exists when the time is too long.
Preferably, the heating temperature in the step 2) is 60-100 ℃, and the heating time is 30-60min. The temperature and time ensure that most, even all, of the NO 2 Is removed.
Preferably, the iron is in excess in step 3).
Preferably, the reaction in step 3) is carried out at room temperature for 48 hours or more. The invention discovers that if the reaction time of iron is less than 48 hours, the defect of insufficient treatment of impurity chloroauric acid exists.
Preferably, step 4) is pH adjusted by adding sodium carbonate, sodium bicarbonate, potassium carbonate, potassium bicarbonate, alkali metal hydroxide or ammonia.
Preferably, the filtration in step 4) employs a microporous membrane of 0.1-0.45 μm to ensure that the impurity ions are removed cleanly.
Preferably, the separation step includes: the step 4) is carried out 90 Sr/ 90 The pH of the Y solution is adjusted to 10-14, and the precipitate is obtained by filtration or centrifugation, and then the precipitate is dissolved with an acid solution 90 Y species solution. The invention preferably adopts a precipitation method to carry out the separation processCompared with other methods, the method has the advantages of reducing radioactive waste, saving raw material cost and being simple to operate. By the above method 90 The purity of Y can reach more than 99.8 percent, and can be used for experimental grade application; further through experimental optimization, the filtering times are increased, and the medical grade can be prepared 90 A Y species.
The invention has the advantages that:
the invention takes waste Sr-90 radioactive source as raw material, and obtains the needed Sr-90 raw material after dissolving and removing impurities, thereby being used for recycling and producing radioactive waste 90 The Y nuclide provides a new method, and the purity can be separated out to be more than 99.8% by adopting a simple precipitation method 90 And the Y nuclide greatly saves the production cost.
Detailed Description
The following describes the embodiments of the present invention in further detail with reference to specific examples.
The following examples are only for illustrating the present invention and are not intended to limit the scope of the present invention.
The experimental methods used in the following examples are conventional methods unless otherwise specified.
Materials, reagents and the like used in the following examples are commercially available unless otherwise specified.
Example 1
(1) Preparation of raw materials
About 2cm of waste Sr-90 radioactive source sheet is taken in experiment 2 Adding small blocks into a 10mL penicillin bottle by using scissors, sequentially adding 3mL of concentrated hydrochloric acid and 1mL of concentrated nitric acid, shaking uniformly, and standing for 4h. Transferring the solution to obtain NO, heating to 95deg.C at a rate of 5 deg.C/min, maintaining for 30 min, and removing NO from the solution 2 . And adding excessive iron into the solution to react for 48 hours, and reducing chloroauric acid with strong oxidability while neutralizing the acid. 10mol/L NaOH solution is added into the solution to adjust the pH to 14, then a microporous filter membrane with the thickness of 0.22 mu m is used for filtering the solution to obtain precipitate, and HCl is slowly added into the solution to adjust the pH to 5. After standing for 14 days 90 Sr and 90 y reaches equilibrium again.
(2) Separation filtration
At equilibrium 90 Sr/ 90 Slowly adding 1mol/L NaOH solution into the Y solution, adjusting the pH value to be 11, sucking the solution by using a 10mL medical needle tube, filtering by using a microporous filter membrane with the thickness of 0.22 mu m, continuously sucking 10mL of 0.1mol/L NaOH solution, slowly cleaning a filter head at the speed of 1mL/min, repeating for 2 times, and finally sucking deionized water and filtering for 2 times.
(3) Acid leaching
Through the above-mentioned operation, 90 y as precipitate Y (OH) 3 Adsorbing on the filter head, sucking 5mL of hydrochloric acid solution with concentration of 0.5mol/L at a concentration of 1mL/min, and washing the filter head to obtain 90 Y species solution.
(4) Nuclear purity examination
Sampling and leaching 90 Y, the radioactivity of the solution is measured by liquid scintillation and at intervals, i.e. half-life assay. The radioactivity was measured over 640 hours, at which time the radioactive impurity was half of the final activity, and the purity of the radionuclide in the stock solution was determined. Obtained by the above method 90 The purity of Y reaches 99.83%, and can be used for experimental grade application.
Comparative example 1
Compared with example 1, the only difference is that: in the preparation of the raw materials, NO is removed without heating the leaching solution 2 The operation is carried out, fe is not used for neutralization, only NaOH is used for neutralization, a light yellow Sr-90-containing solution is obtained as a raw material, a light yellow Y-90 solution is obtained in the subsequent reaction, and the detection of the oxidizing chloroauric acid ion is carried out.
Comparative example 2
Compared with example 1, the only difference is that: in the preparation process of the raw materials, concentrated nitric acid is used for heating and dissolving the waste Sr-90 radioactive source sheet, the obtained Sr-90 is only 5%, and a large amount of AgOH flocculent precipitate is obtained after alkali precipitation, so that the next operation cannot be performed.
Finally, it should be noted that: the above embodiments are only for illustrating the technical solution of the present invention, and are not limiting; although the invention has been described in detail with reference to the foregoing embodiments, it will be understood by those of ordinary skill in the art that: the technical scheme described in the foregoing embodiments can be modified or some technical features thereof can be replaced by equivalents; such modifications and substitutions do not depart from the spirit and scope of the technical solutions of the embodiments of the present invention.
Claims (9)
1. Separation and preparation from waste Sr-90 radioactive source 90 The method for preparing the Y nuclide is characterized by comprising a pretreatment process and a separation process, wherein the pretreatment process sequentially comprises the following steps:
1) In waste Sr-90 radioactive sources 90 Leaching Sr by using aqua regia to obtain leaching liquid;
2) Heating the leachate to remove NO therefrom 2 ；
3) Adding iron into the leaching solution for reaction;
4) Regulating the pH of the leaching solution to 12-14, and filtering or centrifuging to obtain clear liquid;
5) Regulating pH of the clear solution to 4-7, standing for more than 14 days to obtain 90 Sr/ 90 And Y solution.
2. The method of claim 1, wherein the Sr-90 is separated from the waste source 90 The method of the Y nuclide is characterized in that the waste Sr-90 radioactive source is a source sheet of a waste strontium-90 applicator prepared by a powder metallurgy process.
3. The method for separating and preparing the waste Sr-90 radioactive source according to claim 2 90 The method for leaching the Y nuclide is characterized in that the leaching temperature in the step 1) is room temperature, and the leaching time is 1-4h.
4. A process according to any one of claims 1 to 3, wherein the process is carried out by separating from a waste Sr-90 radiation source 90 The method for heating the Y nuclide is characterized in that the heating temperature in the step 2) is 60-100 ℃, and the heating time is 30-60min.
5. The isolated preparation of any of claims 1-4 from a spent Sr-90 radiation source 90 A method for producing a Y-nuclide, characterized in that the iron in step 3) isExcess.
6. The process according to any one of claims 1-5, wherein the process is carried out by separating from a waste Sr-90 radiation source 90 The method for preparing the Y nuclide is characterized in that the temperature of the reaction in the step 3) is room temperature and the time is more than 48 hours.
7. The process according to any one of claims 1-6, wherein the process is carried out by separating from a waste Sr-90 radiation source 90 A process for Y nuclides, characterized in that step 4) the pH is adjusted by adding sodium carbonate, sodium bicarbonate, potassium carbonate, potassium bicarbonate, alkali metal hydroxide or ammonia.
8. The isolated preparation of any of claims 1-7 from a spent Sr-90 radiation source 90 The method for preparing the Y nuclide is characterized in that a microporous filter membrane with the diameter of 0.1-0.45 μm is adopted for the filtration in the step 4).
9. The isolated preparation of any of claims 1-8 from a spent Sr-90 radiation source 90 The method for separating Y nuclide is characterized in that the separation process comprises the following steps: the step 4) is carried out 90 Sr/ 90 The pH of the Y solution is adjusted to 10-14, and the precipitate is obtained by filtration or centrifugation, and then the precipitate is dissolved with an acid solution 90 Y species solution.
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| Application Number | Priority Date | Filing Date | Title |
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| CN202310421155.1A CN116646104A (en) | 2023-04-19 | 2023-04-19 | Separation and preparation from waste Sr-90 radioactive source 90 Method of Y nuclides |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310421155.1A CN116646104A (en) | 2023-04-19 | 2023-04-19 | Separation and preparation from waste Sr-90 radioactive source 90 Method of Y nuclides |
Publications (1)
| Publication Number | Publication Date |
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| CN116646104A true CN116646104A (en) | 2023-08-25 |
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| CN202310421155.1A Pending CN116646104A (en) | 2023-04-19 | 2023-04-19 | Separation and preparation from waste Sr-90 radioactive source 90 Method of Y nuclides |
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| Country | Link |
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| CN (1) | CN116646104A (en) |
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- 2023-04-19 CN CN202310421155.1A patent/CN116646104A/en active Pending
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