CN115612868A - Purification process for separating actinium 225 from thorium, actinium and radium - Google Patents

Purification process for separating actinium 225 from thorium, actinium and radium Download PDF

Info

Publication number
CN115612868A
CN115612868A CN202211149724.3A CN202211149724A CN115612868A CN 115612868 A CN115612868 A CN 115612868A CN 202211149724 A CN202211149724 A CN 202211149724A CN 115612868 A CN115612868 A CN 115612868A
Authority
CN
China
Prior art keywords
actinium
resin
solution
adsorption column
thorium
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
CN202211149724.3A
Other languages
Chinese (zh)
Inventor
肖松涛
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Beijing Health Qihang Technology Co ltd
Original Assignee
Beijing Health Qihang Technology Co ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Beijing Health Qihang Technology Co ltd filed Critical Beijing Health Qihang Technology Co ltd
Priority to CN202211149724.3A priority Critical patent/CN115612868A/en
Publication of CN115612868A publication Critical patent/CN115612868A/en
Pending legal-status Critical Current

Links

Images

Classifications

    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22BPRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02Obtaining thorium, uranium, or other actinides
    • C22B60/0295Obtaining thorium, uranium, or other actinides obtaining other actinides except plutonium
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22BPRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B3/00Extraction of metal compounds from ores or concentrates by wet processes
    • C22B3/20Treatment or purification of solutions, e.g. obtained by leaching
    • C22B3/22Treatment or purification of solutions, e.g. obtained by leaching by physical processes, e.g. by filtration, by magnetic means, or by thermal decomposition
    • C22B3/24Treatment or purification of solutions, e.g. obtained by leaching by physical processes, e.g. by filtration, by magnetic means, or by thermal decomposition by adsorption on solid substances, e.g. by extraction with solid resins
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22BPRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B3/00Extraction of metal compounds from ores or concentrates by wet processes
    • C22B3/20Treatment or purification of solutions, e.g. obtained by leaching
    • C22B3/26Treatment or purification of solutions, e.g. obtained by leaching by liquid-liquid extraction using organic compounds
    • C22B3/38Treatment or purification of solutions, e.g. obtained by leaching by liquid-liquid extraction using organic compounds containing phosphorus
    • C22B3/384Pentavalent phosphorus oxyacids, esters thereof
    • C22B3/3846Phosphoric acid, e.g. (O)P(OH)3

Landscapes

  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Geology (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Manufacturing & Machinery (AREA)
  • Environmental & Geological Engineering (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Geochemistry & Mineralogy (AREA)
  • Treatment Of Liquids With Adsorbents In General (AREA)

Abstract

The invention relates to the field and discloses a purification process for separating actinium 225 from thorium, actinium and radium, which comprises the following steps of S1, preparing an adsorption resin column, respectively weighing appropriate LN series resin and P204 resin, and manufacturing the resin adsorption column; s2, removing a proper amount of solution to be separated, injecting the solution into a centrifuge tube, adding an LN series resin adsorption column, putting the centrifuge tube into a constant-temperature oscillator, reacting for a period of time, and taking out the LN series resin adsorption column to obtain a solution A; s3, adding a proper amount of acid liquor into the solution A obtained in the step S2, adding a P204 resin adsorption column, putting the centrifugal tube into a constant-temperature oscillator for reaction for a period of time, and taking out the P204 resin adsorption column to obtain a solution C; and S4, treating the P204 resin adsorption column in the step S3 by taking a proper amount of eluent to obtain the purified actinium 225 solution, wherein the actinium 225 can be efficiently separated from the thorium and the radium by the process provided by the invention, so that the actinium 225 is purified.

Description

Purification process for separating actinium 225 from thorium, actinium and radium
Technical Field
The invention relates to the field, in particular to a purification process for separating actinium 225 from thorium, actinium and radium.
Background
Nuclear medicine has great application value in both diagnostic and therapeutic applications, where radionuclides for diagnostic or therapeutic use are usually attached to selective biomolecules (polypeptides, antibody fragments or whole antibodies) to deliver imaging or therapeutic doses to targets (tumors or other tissues) in vivo, targeted Alpha Therapy (TAT) is a rapidly developing field that utilizes alpha radionuclides to selectively deliver radiation doses that kill cells to the tumor site, where low penetration ranges (50-90 μm) and high linear mass transfer of alpha particles (tens to hundreds of keV/μm) can maximize destruction of cancer cells with minimal damage to surrounding healthy tissues.
Actinium-0225 has significant potential as a TAT nuclide because of its favorable half-life and decay cascade including multiple short-lived alpha nuclides, which when combined with a biological targeting vector can be used directly for therapy, or as a parent for the daughter nuclide 213Bi (t 1/2=45.6 min), which can also be chelated or complexed for use in vivo.
At the present time, it is known that, 225 the main source of Ac is the parent 229 Th(t 1/2 =7340 a), early stage from 233 U is obtained in reactors as fuel, now produced globally by decay 225 The supply of Ac does not exceed 63GBq (1.7 Ci) [9 ] per year]To is aligned with 225 The Ac demand exceeds the raw material 229 Th can be provided, therefore, in recent years, a different group including the Los Alamos National Laboratory (LANL) has been paired with production 225 Alternative approaches to Ac have been investigated, and one of the most promising approaches is thought to be via intermediate energy (C) ((R))>70 MeV) proton activation 232 Th occur 232 Th (p, x) nuclear reaction, data obtained from LANL, showed proton pairs with energies of 100MeV, 250 μ A 232 Th producing 73.2GBq (1.98 Ci) after 10 days of irradiation 225 Ac, the number of which exceeds that of each research department worldwide 229 Obtained from Th 225 Accumulation of Ac.
Albeit from 232 The Th (p, x) nuclear reaction can produce appreciable quantities 225 Ac, but separation of actinium and radium from irradiated thorium targets is a difficult problem, the irradiation mainly contains three elements Th, ra and Ac, and also generates a series of radioactive isotopes, fission products and a large excess of thorium must be separated from actinium, the separation of thorium and actinium is more difficult, on one hand, the metals thorium and actinium are very different in quality because of the relationship between decay parent and daughter generation, the concentration difference is several orders of magnitude, namely, trace actinium and radium are enriched and separated from a large amount of thorium, on the other hand, thorium and actinium which are both actinium have similar chemical propertiesBecause it is difficult to directly separate Ac from Th due to the interference of high-concentration Th, gradual separation is needed, namely, chemical treatment is carried out on irradiated thorium target through a series of ion separation and extraction chromatographic columns, so that a high-efficiency and rapid chemical separation and purification method of thorium, actinium and radium is sought, which provides a foundation for the research and development of Targeted Alpha Therapy (TAT) and has important significance for the development of radionuclide drugs.
Disclosure of Invention
The invention aims to provide a purification process for separating actinium 225 from thorium, actinium and radium aiming at the defects of the prior art.
The technical purpose of the invention is realized by the following technical scheme: a purification process for separating actinium 225 from thorium, actinium and radium comprises the following steps:
s1, preparing an adsorption resin column, namely respectively weighing appropriate LN series resin and P204 resin, and manufacturing the resin adsorption column;
s2, removing a proper amount of solution to be separated, injecting the solution into a centrifuge tube, adding an LN series resin adsorption column, putting the centrifuge tube into a constant-temperature oscillator, reacting for a period of time, and taking out the LN series resin adsorption column to obtain a solution A;
s3, adding a proper amount of acid liquor into the solution A obtained in the step S2, adding a P204 resin adsorption column, putting the centrifugal tube into a constant-temperature oscillator for reaction for a period of time, and taking out the P204 resin adsorption column to obtain a solution C;
and S4, treating the P204 resin adsorption column in the step S3 by using a proper amount of eluent to obtain the purified actinium 225 solution.
Further, the resin in the step S1 is filled into a column by adopting a wet method, and the resin is put into a beaker filled with ultrapure water to prepare a suspension.
Furthermore, before the resin column filling in the step S1, cotton needs to be plugged at the bottom of the column, silica gel needs to be laid on the cotton, and ultrapure water needs to be used for repeated washing in the resin column filling process.
Further, the step S3 is to add an appropriate amount of nitric acid solution to the solution a until the PH of the solution a is 3.
Further, the step S2 and the step S3 are respectively put into a constant temperature oscillator for reaction for 10-20h.
Further, the LN series resin of step S1 has a particle size of 0.315 to 0.515mm.
Further, the eluent for the P204 resin adsorption column treatment in step S3 in step S4 may be ultrapure water.
Further, the LN series resin adsorption column of step S2 and the solution C of step S3 are subjected to a recovery treatment.
Compared with the prior art, the scheme of the invention has the following beneficial effects: the invention separates the solution by a resin adsorption column prepared by wet column packing, thereby realizing the purification process of actinium 225, wherein, LN series resin with smaller granularity is adopted to adsorb thorium in the solution, and then the solution is adjusted to PH 3, ra and Ra are mixed by a P204 resin adsorption column 225 In the mixed solution of Ac 225 Ac purification and purification process is efficient, and the obtained product 225 The Ac purity is high.
Drawings
FIG. 1 shows the ion concentrations of the solutions after treatment with LN series resin adsorption column of example 1 of the present invention;
FIG. 2 shows the ion concentrations of the solutions after the LN series resin adsorption column treatment in example 2 of the present invention;
FIG. 3 shows the ion concentrations of the solutions after the treatment of the P204 resin adsorption column in example 3 of the present invention;
FIG. 4 shows the ion concentrations of the solutions after the treatment of the P204 resin adsorption column in example 4 of the present invention.
Detailed Description
The invention provides a purification process for separating actinium 225 from thorium, actinium and radium, which comprises the following steps:
s1, preparing an adsorption resin column, namely respectively weighing appropriate LN series resin and P204 resin, and manufacturing the resin adsorption column;
s2, removing a proper amount of solution to be separated, injecting the solution into a centrifuge tube, adding an LN series resin adsorption column, putting the centrifuge tube into a constant temperature oscillator for reaction for a period of time, and taking out the LN series resin adsorption column to obtain a solution A;
step S3, adding a proper amount of acid liquor into the solution A obtained in the step S2, adding a P204 resin adsorption column, putting the centrifugal tube into a constant-temperature oscillator for reacting for a period of time, and taking out the P204 resin adsorption column to obtain a solution C;
and S4, treating the P204 resin adsorption column in the step S3 by taking a proper amount of eluent to obtain the purified actinium 225 solution.
Because it is difficult to directly separate Ac from Th under the interference of high-concentration Th, it is still necessary to separate it step by step, i.e. the irradiated thorium target is chemically treated by a series of extraction chromatographic columns, and it is found by investigation that commercial series LN resin has excellent separation effect on rare earth elements and lanthanide elements, while P204 resin can selectively separate Sr and Y, so it may also have separation effect on Ac and Ra in the same main group. Therefore, the present invention uses these two resins to separate three ions, th, ac and Ra.
Example 1
A purification process for separating actinium 225 from thorium, actinium and radium comprises the following steps:
s1, preparing an adsorption resin column, namely respectively weighing appropriate LN series resin with the granularity of 0.515mm and P204 resin, and manufacturing the resin adsorption column;
s2, removing a proper amount of solution to be separated, injecting the solution into a centrifuge tube, adding an LN series resin adsorption column, putting the centrifuge tube into a constant-temperature oscillator, reacting for a period of time, and taking out the LN series resin adsorption column to obtain a solution A;
s3, adding a proper amount of acid liquor into the solution A in the step S2 to enable the pH value of the solution to be 5, adding a P204 resin adsorption column, putting the centrifugal tube into a constant-temperature oscillator for reaction for a period of time, taking out the P204 resin adsorption column, and obtaining a solution C;
and S4, treating the P204 resin adsorption column in the step S3 by taking a proper amount of eluent to obtain the purified actinium 225 solution.
Example 2
A purification process for separating actinium 225 from thorium, actinium and radium comprises the following steps:
s1, preparing an adsorption resin column, namely respectively weighing appropriate LN series resin with the granularity of 0.315mm and appropriate P204 resin, and manufacturing the resin adsorption column;
s2, removing a proper amount of solution to be separated, injecting the solution into a centrifuge tube, adding an LN series resin adsorption column, putting the centrifuge tube into a constant-temperature oscillator, reacting for a period of time, and taking out the LN series resin adsorption column to obtain a solution A;
step S3, adding a proper amount of acid liquor into the solution A obtained in the step S2 to enable the pH value of the solution to be 4, adding a P204 resin adsorption column, placing the centrifugal tube into a constant-temperature oscillator to react for a period of time, taking out the P204 resin adsorption column, and obtaining a solution C;
and S4, treating the P204 resin adsorption column in the step S3 by taking a proper amount of eluent to obtain the purified actinium 225 solution.
Example 3
A purification process for separating actinium 225 from thorium, actinium and radium comprises the following steps:
s1, preparing an adsorption resin column, namely respectively weighing appropriate LN series resin with the granularity of 0.515mm and P204 resin, and manufacturing the resin adsorption column;
s2, removing a proper amount of solution to be separated, injecting the solution into a centrifuge tube, adding an LN series resin adsorption column, putting the centrifuge tube into a constant temperature oscillator for reaction for a period of time, and taking out the LN series resin adsorption column to obtain a solution A;
step S3, adding a proper amount of acid liquor into the solution A obtained in the step S2 to enable the pH value of the solution to be 5, adding a P204 resin adsorption column, placing the centrifugal tube into a constant-temperature oscillator to react for a period of time, taking out the P204 resin adsorption column, and obtaining a solution C;
and S4, treating the P204 resin adsorption column in the step S3 by using a proper amount of eluent to obtain the purified actinium 225 solution.
Example 4
A purification process for separating actinium 225 from thorium, actinium and radium comprises the following steps:
s1, preparing an adsorption resin column, namely respectively weighing an appropriate amount of LN series resin with the granularity of 0.315 and P204 resin, and manufacturing the resin adsorption column;
s2, removing a proper amount of solution to be separated, injecting the solution into a centrifuge tube, adding an LN series resin adsorption column, putting the centrifuge tube into a constant temperature oscillator for reaction for a period of time, and taking out the LN series resin adsorption column to obtain a solution A;
s3, adding a proper amount of acid liquor into the solution A in the step S2 to enable the pH value of the solution to be 3, adding a P204 resin adsorption column, putting the centrifugal tube into a constant-temperature oscillator for reaction for a period of time, taking out the P204 resin adsorption column, and obtaining a solution C;
and S4, treating the P204 resin adsorption column in the step S3 by taking a proper amount of eluent to obtain the purified actinium 225 solution.
Each of the solutions of examples 1 to 4 was individually taken, and the effluent of each solution was measured for Th, ra, and, 225 Ac ion concentration is shown in FIGS. 1-4, where the triangular symbol curve represents thorium, the circular curve represents actinium 225, and the rectangular curve represents radium, and it can be seen from FIGS. 1-4 that the LN series resin has different concentration ratios of Th, ra, and, 225 Three ions of Ac have good separation effect; however, the LN resin having a large particle size at a high concentration ratio had a poor separation effect, while the LN resin having a small particle size still had a good separation effect, and the P204 resin had a pH =3-5 in the range of Ra, 225 Ac was excellent in separation effect, and was most preferable at pH = 3.
The present embodiment is only for explaining the present invention, and it is not limited to the present invention, and those skilled in the art can make modifications without inventive contribution to the present embodiment as required after reading the present specification, but all of them are protected by patent law within the scope of the present invention.

Claims (8)

1. A purification process for separating actinium 225 from thorium, actinium and radium is characterized by comprising the following steps:
s1, preparing an adsorption resin column, namely respectively weighing appropriate LN series resin and P204 resin, and manufacturing the resin adsorption column;
s2, removing a proper amount of solution to be separated, injecting the solution into a centrifuge tube, adding an LN series resin adsorption column, putting the centrifuge tube into a constant-temperature oscillator, reacting for a period of time, and taking out the LN series resin adsorption column to obtain a solution A;
s3, adding a proper amount of acid liquor into the solution A obtained in the step S2, adding a P204 resin adsorption column, putting the centrifugal tube into a constant-temperature oscillator for reaction for a period of time, and taking out the P204 resin adsorption column to obtain a solution C;
and S4, treating the P204 resin adsorption column in the step S3 by taking a proper amount of eluent to obtain the purified actinium 225 solution.
2. The purification process for separating actinium 225 from thorium, actinium and radium as claimed in claim 1, wherein the resin of step S1 is packed into a column by a wet method, and the resin is put into a beaker filled with ultrapure water to prepare a suspension.
3. The purification process for separating actinium 225 from thorium, actinium and radium as claimed in claim 2, wherein the cotton is packed at the bottom of the resin column and is paved with silica gel before the resin column is packed in the step S1, and the resin column is repeatedly washed by using ultrapure water during the resin column packing process.
4. A purification process for the separation of actinium 225 from thorium, actinium and radium according to claim 1, characterized in that the step S3 consists in adding a suitable amount of nitric acid solution to solution A until the pH of solution A is 3.
5. The purification process for separation of actinium 225 from thorium, actinium and radium according to claim 1, characterized in that the steps S2 and S3 respectively put the centrifuge tube into a constant temperature oscillator for reaction for 10-20h.
6. A purification process for the separation of actinium 225 from thorium, actinium and radium according to claim 1, characterised in that the particle size of the LN series resin of step S1 is 0.315-0.515mm.
7. The purification process for separating actinium 225 from thorium, actinium and radium as claimed in claim 1, wherein the eluent used in the step S4 for the treatment of the P204 resin adsorption column of the step S3 can be ultrapure water.
8. A purification process for the separation of actinides 225 from thorium, actinides and radium according to claim 1, characterized in that: the LN series resin adsorption column of step S2 and the solution C of step S3 are also subjected to a recovery treatment.
CN202211149724.3A 2022-09-21 2022-09-21 Purification process for separating actinium 225 from thorium, actinium and radium Pending CN115612868A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202211149724.3A CN115612868A (en) 2022-09-21 2022-09-21 Purification process for separating actinium 225 from thorium, actinium and radium

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202211149724.3A CN115612868A (en) 2022-09-21 2022-09-21 Purification process for separating actinium 225 from thorium, actinium and radium

Publications (1)

Publication Number Publication Date
CN115612868A true CN115612868A (en) 2023-01-17

Family

ID=84859545

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202211149724.3A Pending CN115612868A (en) 2022-09-21 2022-09-21 Purification process for separating actinium 225 from thorium, actinium and radium

Country Status (1)

Country Link
CN (1) CN115612868A (en)

Citations (17)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB810542A (en) * 1944-12-30 1959-03-18 Atomic Energy Authority Uk Recovery of protoactinium
US3459634A (en) * 1966-09-19 1969-08-05 Gen Electric Radioisotope processing
US5809394A (en) * 1996-12-13 1998-09-15 Battelle Memorial Institute Methods of separating short half-life radionuclides from a mixture of radionuclides
US20060213329A1 (en) * 2004-09-24 2006-09-28 Battelle Energy Alliance, Llc Actinium radioisotope products of enhanced purity
US20100018347A1 (en) * 2006-10-05 2010-01-28 Holden Charles S Separation of radium and rare earth elements from monazite
US20100104489A1 (en) * 2006-09-08 2010-04-29 Actinium Pharmaceuticals Inc. Method for the purification of radium from different sources
US20140072485A1 (en) * 2012-09-13 2014-03-13 Ut-Battelle, Llc Methods for separating medical isotopes using ionic liquids
US20150292061A1 (en) * 2014-04-09 2015-10-15 Los Alamos National Security, Llc Separation of protactinum, actinium, and other radionuclides from proton irradiated thorium target
WO2017157355A1 (en) * 2016-03-16 2017-09-21 Ceske Vysoke Uceni Technicke V Praze Method for isolation of ac from mixture of radium, actinium and thorium
RU2716272C1 (en) * 2019-10-15 2020-03-11 Общество с ограниченной ответственностью «Научно-технический центр инноваций» (ООО "НТЦИ") Method of producing actinium-227, thorium-228 and thorium-229 from irradiated radium-226
US20200082956A1 (en) * 2018-09-06 2020-03-12 Uchicago Argonne, Llc. Sytem and method for collecting and isolating radiosotopes
RU2725414C1 (en) * 2019-12-12 2020-07-02 Федеральное государственное бюджетное учреждение науки Институт ядерных исследований Российской академии наук (ИЯИ РАН) Method of producing actinium-225
US20210027905A1 (en) * 2018-03-26 2021-01-28 Andrew Kyle Henderson ROBERTSON Systems, apparatus and methods for separating actinium, radium, and thorium
CN113066598A (en) * 2021-03-25 2021-07-02 中国科学院近代物理研究所 Irradiation from high-energy proton beam232Separation and purification in spallation reaction caused by Th target223Method for Ra
CN113874960A (en) * 2019-06-25 2021-12-31 欧盟委员会 By226Production of radium225Process for actinium
JP2022062962A (en) * 2020-10-09 2022-04-21 日本医用アイソトープ株式会社 Method for producing actinium 225
US20220215979A1 (en) * 2021-01-05 2022-07-07 Korea Advanced Institute Of Science And Technology Method and system for producing medical radioisotopes

Patent Citations (17)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB810542A (en) * 1944-12-30 1959-03-18 Atomic Energy Authority Uk Recovery of protoactinium
US3459634A (en) * 1966-09-19 1969-08-05 Gen Electric Radioisotope processing
US5809394A (en) * 1996-12-13 1998-09-15 Battelle Memorial Institute Methods of separating short half-life radionuclides from a mixture of radionuclides
US20060213329A1 (en) * 2004-09-24 2006-09-28 Battelle Energy Alliance, Llc Actinium radioisotope products of enhanced purity
US20100104489A1 (en) * 2006-09-08 2010-04-29 Actinium Pharmaceuticals Inc. Method for the purification of radium from different sources
US20100018347A1 (en) * 2006-10-05 2010-01-28 Holden Charles S Separation of radium and rare earth elements from monazite
US20140072485A1 (en) * 2012-09-13 2014-03-13 Ut-Battelle, Llc Methods for separating medical isotopes using ionic liquids
US20150292061A1 (en) * 2014-04-09 2015-10-15 Los Alamos National Security, Llc Separation of protactinum, actinium, and other radionuclides from proton irradiated thorium target
WO2017157355A1 (en) * 2016-03-16 2017-09-21 Ceske Vysoke Uceni Technicke V Praze Method for isolation of ac from mixture of radium, actinium and thorium
US20210027905A1 (en) * 2018-03-26 2021-01-28 Andrew Kyle Henderson ROBERTSON Systems, apparatus and methods for separating actinium, radium, and thorium
US20200082956A1 (en) * 2018-09-06 2020-03-12 Uchicago Argonne, Llc. Sytem and method for collecting and isolating radiosotopes
CN113874960A (en) * 2019-06-25 2021-12-31 欧盟委员会 By226Production of radium225Process for actinium
RU2716272C1 (en) * 2019-10-15 2020-03-11 Общество с ограниченной ответственностью «Научно-технический центр инноваций» (ООО "НТЦИ") Method of producing actinium-227, thorium-228 and thorium-229 from irradiated radium-226
RU2725414C1 (en) * 2019-12-12 2020-07-02 Федеральное государственное бюджетное учреждение науки Институт ядерных исследований Российской академии наук (ИЯИ РАН) Method of producing actinium-225
JP2022062962A (en) * 2020-10-09 2022-04-21 日本医用アイソトープ株式会社 Method for producing actinium 225
US20220215979A1 (en) * 2021-01-05 2022-07-07 Korea Advanced Institute Of Science And Technology Method and system for producing medical radioisotopes
CN113066598A (en) * 2021-03-25 2021-07-02 中国科学院近代物理研究所 Irradiation from high-energy proton beam232Separation and purification in spallation reaction caused by Th target223Method for Ra

Non-Patent Citations (3)

* Cited by examiner, † Cited by third party
Title
刘文刚;刘卉;李国占;周红英;肖志斌;涂家润;李惠民;: "离子交换树脂在地质样品Sr-Nd同位素测定中的应用", 地质学报, no. 11 *
徐岩冰, 杨维凡, 袁双贵, 牛雁宁, 丁华杰: "液-液萃取从Th中分离Ac", 科学技术与工程, no. 14 *
杨强;胡志方;严陈昌;江洪林;尹延西;: "钍的萃取法提取进展与金属钍制备技术", 矿冶, no. 01 *

Similar Documents

Publication Publication Date Title
Lebedev et al. Radiochemical separation of no-carrier-added 177Lu as produced via the 176Ybn, γ177Yb→ 177Lu process
US6716353B1 (en) Method for preparing high specific activity 177Lu
KR20130111931A (en) Isotope preparation method
CN110544548B (en) Production based on electron accelerator99Molybdenum-technetium treatment and separation method for Mo
Kazakov et al. Separation of radioisotopes of terbium from a europium target irradiated by 27 MeV α-particles
Qaim et al. Positron-emitting radionuclides for applications, with special emphasis on their production methodologies for medical use
Yano et al. Evaluation and Application of Alumina-Based Rb-82 Generators Charged with High
Schmidt et al. Current State of 44Ti/44Sc Radionuclide Generator Systems and Separation Chemistry
Kawabata et al. Large scale production of 64 Cu and 67 Cu via the 64 Zn (n, p) 64 Cu and 68 Zn (n, np/d) 67 Cu reactions using accelerator neutrons
RU2768732C2 (en) Method of producing isotope
RU2430440C1 (en) Bismuth-212 radionuclide obtaining method
CN115612868A (en) Purification process for separating actinium 225 from thorium, actinium and radium
RU2439727C1 (en) Method to produce radionuclide bismuth-212
US6974563B2 (en) Ion exchange materials for the separation of 90Y from 90SR
Van der Walt et al. Thick targets for the production of some radionuclides and the chemical processing of these targets at iThemba LABS
Zona et al. Wet-chemistry method for the separation of no-carrier-added 211 At/211g Po from 209 Bi target irradiated by alpha-beam in cyclotron
Shivarudrappa et al. High purity materials as targets for radioisotope production: Needs and challenges
Mansur et al. Separation of yttrium-90 from strontium-90 via colloid formation
RU2199165C1 (en) Method for producing thorium (starting material) radionuclide for making therapeutic preparation based on bismuth radionuclide
Vosoughi et al. Investigation of radiolabeling efficacy by enhancement of the chemical form of no carrier added 177Lu isolated by electro amalgamation process
RU2210125C2 (en) Method of preparing radionuclide thorium-229 - starting material for preparation of therapeutic agent based on radionuclide bismuth-213
Knapp Jr The development and use of radionuclide generators in nuclear medicine. Recent advances and future perspectives
da Silva et al. Study of the production of 177Lu through 176Yb (n, γ) 177Yb→ 177Lu nuclear reaction
Nurtdinov et al. Synthesis of 177 Lu-based bioconjugate for radioimmunotherapy and evaluation of its stability in physiological media
Salek et al. Isolation of Gadalonium/Terbium using Extraction chromatography approach for therapeutic issues

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
RJ01 Rejection of invention patent application after publication
RJ01 Rejection of invention patent application after publication

Application publication date: 20230117