WO2005089912A1 - Gallium-68 - Google Patents
Gallium-68 Download PDFInfo
- Publication number
- WO2005089912A1 WO2005089912A1 PCT/IB2005/050843 IB2005050843W WO2005089912A1 WO 2005089912 A1 WO2005089912 A1 WO 2005089912A1 IB 2005050843 W IB2005050843 W IB 2005050843W WO 2005089912 A1 WO2005089912 A1 WO 2005089912A1
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- acid
- germanium
- anion exchanger
- gallium
- anions
- 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.)
- Ceased
Links
Classifications
-
- 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
- G21G4/08—Radioactive sources other than neutron sources characterised by constructional features specially adapted for medical application
-
- A—HUMAN NECESSITIES
- A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
- A61K—PREPARATIONS FOR MEDICAL, DENTAL OR TOILETRY PURPOSES
- A61K51/00—Preparations containing radioactive substances for use in therapy or testing in vivo
- A61K51/12—Preparations containing radioactive substances for use in therapy or testing in vivo characterised by a special physical form, e.g. emulsion, microcapsules, liposomes, characterized by a special physical form, e.g. emulsions, dispersions, microcapsules
- A61K51/1282—Devices used in vivo and carrying the radioactive therapeutic or diagnostic agent, therapeutic or in vivo diagnostic kits, stents
Definitions
- THIS INVENTION relates to gallium-68.
- it relates to a method of obtaining gallium-68, to a method of preparing a preparation containing a radioisotope for use in therapy or diagnostic testing in vivo, and to a germanium- 68/gallium-68 generator.
- Gallium is a soft silvery metallic element belonging to Group MIA of the periodic table. It has two stable isotopes, namely gallium-69 and gallium-71 , seven radioisotopes with half-lives longer than 1 hour, and 15 radioisotopes with half-lives ranging from milliseconds to minutes. This invention relates to the gallium-68 radioisotope.
- a method of obtaining gallium-68 including contacting an anion exchanger, comprising a tertiary and/or a quaternary ammonium functional group, with germanium-68 anions and retaining the germanium- 68 anions on the anion exchanger; and after a decay period, eluting gallium-68 from the anion exchanger, the gallium-68 being formed by the germanium-68 decaying.
- the anion exchanger may be an organic or an inorganic anion exchanger.
- the anion exchanger is a macroporous resin available under the trade name AG MP-1 and produced by Bio-Rad of Richmond, California, USA. This resin is a strongly basic macroporous anion exchanger with a styrene- divinylbenzene copolymer matrix containing a quaternary amino group as a functional group.
- Contacting the anion exchanger with the germanium-68 anions typically includes contacting a solution containing germanium-68 anions with the anion exchanger thereby to adsorb the germanium-68 anions on the anion exchanger.
- the solution may be an acid solution, an aqueous solution or an alkaline solution.
- Anions in the solution in contact with the anion exchanger are thus preferentially retained by the tertiary or quaternary amino group of the anion exchanger.
- the extent to which the anions are retained depends on various factors, such as the ionic species (the more negative the charge, the more strongly it is retained by the anion exchanger), pH and the presence of complexing agents.
- the germanium-68 solution may have a pH between about 0 and about 7, preferably between about 1 and about 3, e.g. about 2.
- the germanium-68 may thus be dissolved in an acid.
- the acid may be selected from the group of acids consisting of hydrofluoric acid, hydrochloric acid, hydrobromic acid, sulphuric acid, nitric acid, perchloric acid, phosphoric acid, acetic acid, citric acid, formic acid, tartaric acid and compositions of two or more of these.
- the acid is hydrofluoric acid.
- the acid may have an acid concentration between about 10 "7 molar and about 10 molar, preferably between about 0.001 molar and about 1 molar, more preferably between about 0.001 molar and about 0.1 molar, e.g. about 0.01 molar.
- the gallium-68 may be eluted from the anion exchanger with an eluant which has a pH between about 0 and about 7, preferably between about 1 and about 3, e.g. about 2.
- the eluant may be an aqueous sodium chloride or sodium citrate solution.
- the solution may have a sodium chloride or sodium citrate concentration between about 0.1 % and about 5 % by mass, preferably between about 0.5 % and about 2 % by mass, e.g. about 0.9 % by mass.
- the eluant may be an acid.
- the acid may be selected from the group of acids consisting of hydrofluoric acid, hydrochloric acid, hydrobromic acid, sulphuric acid, nitric acid, perchloric acid, phosphoric acid, acetic acid, citric acid, formic acid, tartaric acid and compositions of two or more of these.
- the eluant is hydrofluoric acid.
- the acid may have an acid concentration between about 10 "7 molar and about 10 molar, preferably between about 0.001 molar and about 1 molar, more preferably between about 0.001 molar and about 0.1 molar, e.g. about 0.01 molar.
- the decay period may range from a few hours up to about one or two days, e.g. 24 hours.
- the process of the invention may have an efficiency of more than 80 %, typically more than 90 %, where the efficiency is the proportion of the gallium-68, formed by the decay of the germanium-68, which is obtained by the elution process, usually expressed as a percentage, and calculated as:
- % efficiency 100 x (activity of 68 Ga eluted) ⁇ (activity of available 68 Ga formed by decay of 68 Ge)
- the invention extends to a method of preparing a preparation containing a radioisotope for use in therapy or diagnostic testing in vivo, the method including obtaining gallium-68 in accordance with a method as hereinbefore described; and attaching eluted gallium-68 to a carrier to form a preparation containing a radioisotope suitable for use in therapy or diagnostic testing in vivo.
- the carrier may be a complexing reagent (such as a citrate), or a peptide (containing a complex forming group, such as DTPA or DOTA) or a monoclonal antibody (containing a complex forming group, such as DTPA or DOTA).
- the gallium-68 whilst still present in the eluate, may be attached to the carrier.
- the carrier may be labelled with the gallium-68 in the eluate.
- This may include adding the carrier, e.g. a peptide, to the eluate and then adding other reagents, such as a buffer, or vice versa, lf necessary, the eluate may be further treated, e.g. by heating.
- the reaction product is separated from any free gallium-68 and any unreacted or unwanted reagents, such as chemicals which had been used to prepare the buffer.
- the separated reaction product may be converted into an appropriate formulation, such as in a 0.9 % sodium chloride solution, to obtain a radiopharmaceutical or a preparation containing a radioisotope for use in therapy or diagnostic testing in vivo.
- the preparation may be suitable for use in positron emission tomography (PET) using a PET camera or in single photon tomography (SPECT) using a coincidence camera.
- PET positron emission tomography
- SPECT single photon tomography
- the invention extends to a germanium-68/gallium-68 generator, the generator including a vessel which contains an anion exchanger, comprising a tertiary and/or a quaternary ammonium functional group, with germanium-68 anions adsorbed onto the anion exchanger.
- the vessel is an elongate vessel having an inlet and an outlet which are longitudinally spaced, to allow a liquid to be passed through the anion exchanger in the vessel.
- the vessel may be a polyethylene or glass column.
- the generator may include a lead or lead-lined housing within which the vessel is housed.
- EXAMPLE 1 solution pumped through a 2.0 ml AG MP-1 resin column (the resin was converted to the fluoride form and equilibrated with 1.0 M hydrofluoric acid prior to the sorption step).
- the beaker was rinsed twice with 5 ml of 1.0 M hydrofluoric acid and the solution each time pumped through the resin column. 10 ml of 1.0 M hydrofluoric acid was then pumped through the resin column.
- the column was set aside for 24 hours and the 68 Ga, formed by decay of the 68 Ge, eluted with three portions of 5.0 ml of 1.0 M hydrofluoric acid.
- the eluate was collected in a vial, the 68 Ga content measured and the elution efficiency calculated.
- 68 Ga was eluted daily over a period of 3 weeks and the average efficiency was > 90 %. No 68 Ge break-through was found after the series of elutions since no 68 Ge activity was found in the vials.
- the generator of the invention including an anion exchanger resin column (such as AG MP-1) and loaded with germanium-68 from an acid solution, such as a hydrofluoric acid solution, with a concentration ranging from 0.1 to 1 molar hydrofluoric acid, can be used efficiently to obtain gallium-68 by eluting the gallium-68 with an acid solution, such as hydrofluoric acid.
- an anion exchanger resin column such as AG MP-1
- germanium-68 from an acid solution such as a hydrofluoric acid solution
- an acid solution such as hydrofluoric acid solution
- the invention provides an elegant method to generate gallium-68, particularly for the preparation of radioactive pharmaceuticals and materials for diagnostic imaging or testing in vivo or cancer therapy.
- the method and generator of the invention as illustrated, provide a higher elution efficiency than any conventional method or generator of which the Applicant is aware.
- the eluate containing the gallium-68 can be used, with a buffer, to produce a radioactive pharmaceutical for therapy, or testing or diagnostic material, without having to evaporate the acid or, in some other way, getting rid of the acid before the gallium-68 is attached to a carrier or active ingredient or testing material.
Landscapes
- Health & Medical Sciences (AREA)
- Chemical & Material Sciences (AREA)
- Physics & Mathematics (AREA)
- Optics & Photonics (AREA)
- Animal Behavior & Ethology (AREA)
- General Health & Medical Sciences (AREA)
- Medicinal Chemistry (AREA)
- Pharmacology & Pharmacy (AREA)
- Epidemiology (AREA)
- Life Sciences & Earth Sciences (AREA)
- Heart & Thoracic Surgery (AREA)
- Dispersion Chemistry (AREA)
- Public Health (AREA)
- Veterinary Medicine (AREA)
- Chemical Kinetics & Catalysis (AREA)
- General Chemical & Material Sciences (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Medicines Containing Antibodies Or Antigens For Use As Internal Diagnostic Agents (AREA)
Abstract
A method of obtaining gallium-68 includes contacting an anion exchanger, comprising a tertiary and/or a quaternary ammonium functional group, with germanium-68 anions, retaining the germanium-68 anions on the anion exchanger and, after a decay period, eluting gallium-68 from the anion exchanger. The gallium-68 is thus formed by the germanium-68, decaying.
Description
GALLIUM-68
THIS INVENTION relates to gallium-68. In particular, it relates to a method of obtaining gallium-68, to a method of preparing a preparation containing a radioisotope for use in therapy or diagnostic testing in vivo, and to a germanium- 68/gallium-68 generator.
Gallium is a soft silvery metallic element belonging to Group MIA of the periodic table. It has two stable isotopes, namely gallium-69 and gallium-71 , seven radioisotopes with half-lives longer than 1 hour, and 15 radioisotopes with half-lives ranging from milliseconds to minutes. This invention relates to the gallium-68 radioisotope.
According to one aspect of the invention, there is provided a method of obtaining gallium-68, the method including contacting an anion exchanger, comprising a tertiary and/or a quaternary ammonium functional group, with germanium-68 anions and retaining the germanium- 68 anions on the anion exchanger; and after a decay period, eluting gallium-68 from the anion exchanger, the gallium-68 being formed by the germanium-68 decaying.
The anion exchanger may be an organic or an inorganic anion exchanger. In one embodiment of the invention, the anion exchanger is a macroporous resin available under the trade name AG MP-1 and produced by Bio-Rad of Richmond, California, USA. This resin is a strongly basic macroporous anion exchanger with a styrene- divinylbenzene copolymer matrix containing a quaternary amino group as a functional group.
Contacting the anion exchanger with the germanium-68 anions typically includes contacting a solution containing germanium-68 anions with the anion exchanger thereby to adsorb the germanium-68 anions on the anion exchanger. The solution may be an acid solution, an aqueous solution or an alkaline solution. Anions in the solution in contact with the anion exchanger are thus preferentially retained by the tertiary or quaternary amino group of the anion exchanger. The extent to which the anions are retained depends on various factors, such as the ionic species (the more negative the charge, the more strongly it is retained by the anion exchanger), pH and the presence of complexing agents.
The germanium-68 solution may have a pH between about 0 and about 7, preferably between about 1 and about 3, e.g. about 2.
The germanium-68 may thus be dissolved in an acid. The acid may be selected from the group of acids consisting of hydrofluoric acid, hydrochloric acid, hydrobromic acid, sulphuric acid, nitric acid, perchloric acid, phosphoric acid, acetic acid, citric acid, formic acid, tartaric acid and compositions of two or more of these. In one embodiment of the invention, the acid is hydrofluoric acid. The acid may have an acid concentration between about 10"7 molar and about 10 molar, preferably between about 0.001 molar and about 1 molar, more preferably between about 0.001 molar and about 0.1 molar, e.g. about 0.01 molar.
The gallium-68 may be eluted from the anion exchanger with an eluant which has a pH between about 0 and about 7, preferably between about 1 and about 3, e.g. about 2.
The eluant may be an aqueous sodium chloride or sodium citrate solution. The solution may have a sodium chloride or sodium citrate concentration between about 0.1 % and about 5 % by mass, preferably between about 0.5 % and about 2 % by mass, e.g. about 0.9 % by mass.
Instead, the eluant may be an acid. The acid may be selected from the group of acids consisting of hydrofluoric acid, hydrochloric acid, hydrobromic acid,
sulphuric acid, nitric acid, perchloric acid, phosphoric acid, acetic acid, citric acid, formic acid, tartaric acid and compositions of two or more of these. In one embodiment of the invention, the eluant is hydrofluoric acid. The acid may have an acid concentration between about 10"7 molar and about 10 molar, preferably between about 0.001 molar and about 1 molar, more preferably between about 0.001 molar and about 0.1 molar, e.g. about 0.01 molar.
The method may include forming germanium-68 from target material comprising natural or enriched gallium (i.e. gallium-69 or gallium-71) by bombardment of the target material with a proton beam, via the nuclear reaction aGa(p,xn)68Ge (a = natural, 69 or 71). After the bombardment, germanium-68 is separated from the target material and purified from any remaining target material and other unwanted radioisotopes, using methods known to those skilled in the art.
The decay period may range from a few hours up to about one or two days, e.g. 24 hours.
Advantageously, the process of the invention may have an efficiency of more than 80 %, typically more than 90 %, where the efficiency is the proportion of the gallium-68, formed by the decay of the germanium-68, which is obtained by the elution process, usually expressed as a percentage, and calculated as:
% efficiency = 100 x (activity of 68Ga eluted) ÷ (activity of available 68Ga formed by decay of 68Ge)
The invention extends to a method of preparing a preparation containing a radioisotope for use in therapy or diagnostic testing in vivo, the method including obtaining gallium-68 in accordance with a method as hereinbefore described; and attaching eluted gallium-68 to a carrier to form a preparation containing a radioisotope suitable for use in therapy or diagnostic testing in vivo.
The carrier may be a complexing reagent (such as a citrate), or a peptide (containing a complex forming group, such as DTPA or DOTA) or a monoclonal antibody (containing a complex forming group, such as DTPA or DOTA). The gallium-68, whilst still present in the eluate, may be attached to the carrier. In other words, the carrier may be labelled with the gallium-68 in the eluate. This may include adding the carrier, e.g. a peptide, to the eluate and then adding other reagents, such as a buffer, or vice versa, lf necessary, the eluate may be further treated, e.g. by heating. Typically, the reaction product is separated from any free gallium-68 and any unreacted or unwanted reagents, such as chemicals which had been used to prepare the buffer. Finally, the separated reaction product may be converted into an appropriate formulation, such as in a 0.9 % sodium chloride solution, to obtain a radiopharmaceutical or a preparation containing a radioisotope for use in therapy or diagnostic testing in vivo.
The preparation may be suitable for use in positron emission tomography (PET) using a PET camera or in single photon tomography (SPECT) using a coincidence camera. The invention extends to a germanium-68/gallium-68 generator, the generator including a vessel which contains an anion exchanger, comprising a tertiary and/or a quaternary ammonium functional group, with germanium-68 anions adsorbed onto the anion exchanger. Preferably, the vessel is an elongate vessel having an inlet and an outlet which are longitudinally spaced, to allow a liquid to be passed through the anion exchanger in the vessel. The vessel may be a polyethylene or glass column.
The generator may include a lead or lead-lined housing within which the vessel is housed.
The invention will now be described by way of the following examples.
EXAMPLE 1
solution pumped through a 2.0 ml AG MP-1 resin column (the resin was converted to the fluoride form and equilibrated with 1.0 M hydrofluoric acid prior to the sorption step). The beaker was rinsed twice with 5 ml of 1.0 M hydrofluoric acid and the solution each time pumped through the resin column. 10 ml of 1.0 M hydrofluoric acid was then pumped through the resin column. The column was set aside for 24 hours and the 68Ga, formed by decay of the 68Ge, eluted with three portions of 5.0 ml of 1.0 M hydrofluoric acid. The eluate was collected in a vial, the 68Ga content measured and the elution efficiency calculated. 68Ga was eluted daily over a period of 3 weeks and the average efficiency was > 90 %. No 68Ge break-through was found after the series of elutions since no 68Ge activity was found in the vials.
EXAMPLE 2 In a similar experiment to the experiment conducted in Example 1 , 0.1 M hydrofluoric acid was used instead of 1.0 M hydrofluoric acid and the elution efficiency was also found to be > 90 %.
The aforementioned examples clearly indicate that the generator of the invention, including an anion exchanger resin column (such as AG MP-1) and loaded with germanium-68 from an acid solution, such as a hydrofluoric acid solution, with a concentration ranging from 0.1 to 1 molar hydrofluoric acid, can be used efficiently to obtain gallium-68 by eluting the gallium-68 with an acid solution, such as hydrofluoric acid.
The invention provides an elegant method to generate gallium-68, particularly for the preparation of radioactive pharmaceuticals and materials for diagnostic imaging or testing in vivo or cancer therapy. The method and generator of the invention, as illustrated, provide a higher elution efficiency than any conventional method or generator of which the Applicant is aware. Advantageously, when using an acid as the eluting agent, the eluate containing the gallium-68 can be used, with a buffer, to produce a radioactive pharmaceutical for therapy, or testing or diagnostic material, without having to evaporate the acid or, in some other way, getting rid of the acid before the gallium-68 is attached to a carrier or active ingredient or testing material.
Claims
1. A method of obtaining gallium-68, the method including contacting an anion exchanger, comprising a tertiary and/or a quaternary ammonium functional group, with germanium-68 anions and retaining the germanium- 68 anions on the anion exchanger; and after a decay period, eluting gallium-68 from the anion exchanger, the gallium-68 being formed by the germanium-68 decaying.
2. The method as claimed in claim 1 , in which the anion exchanger is a strongly basic macroporous anion exchanger with a styrene-divinylbenzene copolymer matrix containing a quaternary amino group as a functional group.
3. The method as claimed in claim 1 or claim 2, in which contacting the anion exchanger with the germanium-68 anions includes contacting a solution containing germanium-68 anions with the anion exchanger thereby to adsorb the germanium-68 anions on the anion exchanger, the germanium-68 solution having a pH between about 0 and about 7.
4. The method as claimed in claim 3, in which the germanium-68 solution has a pH between about 1 and about 3.
5. The method as claimed in any one of the preceding claims, in which the germanium-68 is dissolved in an acid selected from the group of acids consisting of hydrofluoric acid, hydrochloric acid, hydrobromic acid, sulphuric acid, nitric acid, perchloric acid, phosphoric acid, acetic acid, citric acid, formic acid, tartaric acid and compositions of two or more of these.
6. The method as claimed in claim 5, in which the acid is hydrofluoric acid.
7. The method as claimed in any one of the preceding claims, in which the gallium-68 is eluted from the anion exchanger with an eluant which has a pH between about 0 and about 7.
8. The method as claimed in claim 7, in which the eluant has a pH between about 1 and about 3.
9. The method as claimed in claim 7 or claim 8, in which the eluant is an aqueous sodium chloride or sodium citrate solution.
10. The method as claimed in claim 7 or claim 8, in which the eluant is an acid selected from the group of acids consisting of hydrofluoric acid, hydrochloric acid, hydrobromic acid, sulphuric acid, nitric acid, perchloric acid, phosphoric acid, acetic acid, citric acid, formic acid, tartaric acid and compositions of two or more of these.
11. The method as claimed in claim 10, in which the eluant is hydrofluoric acid.
12. A method of preparing a preparation containing a radioisotope for use in therapy or diagnostic testing in vivo, the method including obtaining gallium-68 in accordance with a method as claimed in any one of claims 1 to 11 inclusive; and attaching eluted gallium-68 to a carrier to form a preparation containing a radioisotope suitable for use in therapy or diagnostic testing in vivo.
13. The method as claimed in claim 12, in which the gallium-68 is attached to the carrier whilst the gallium-68 is still in the eluate.
14. A germanium-68/gallium-68 generator, the generator including a vessel which contains an anion exchanger, comprising a tertiary and/or a quaternary ammonium functional group, with germanium-68 anions adsorbed onto the anion exchanger.
15. The generator as claimed in claim 14, in which the vessel is an elongate vessel having an inlet and an outlet which are longitudinally spaced, to allow a liquid to be passed through the anion exchanger in the vessel.
16. The generator as claimed in claim 14 or claim 15, in which the vessel is a polyethylene or glass column.
17. The generator as claimed in any one of claims 14 to 16 inclusive, which includes a lead or lead-lined housing within which the vessel is housed.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| ZA2004/2065 | 2004-03-15 | ||
| ZA200402065 | 2004-03-15 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| WO2005089912A1 true WO2005089912A1 (en) | 2005-09-29 |
Family
ID=34961168
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| PCT/IB2005/050843 Ceased WO2005089912A1 (en) | 2004-03-15 | 2005-03-08 | Gallium-68 |
Country Status (1)
| Country | Link |
|---|---|
| WO (1) | WO2005089912A1 (en) |
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| RU2331439C1 (en) * | 2007-03-22 | 2008-08-20 | Закрытое акционерное общество "Циклотрон" | Method of obtaining radionuclide generator of gallium-68 |
| DE102009007799A1 (en) * | 2009-02-06 | 2010-08-26 | ITM Isotopen Technologien München AG | Molecule for the functionalization of a carrier, binding of a radionuclide to the carrier and radionuclide generator for the production of the radionuclide and production method |
| CN101593567B (en) * | 2009-06-18 | 2011-10-26 | 天津赛德生物制药有限公司 | Preparation method of 68Ge sealed radioactive source |
| WO2011033120A3 (en) * | 2009-09-21 | 2011-11-03 | Ge Healthcare Limited | Method for obtaining 68ga |
| JP2019060893A (en) * | 2013-06-27 | 2019-04-18 | キュリウム ユーエス エルエルシー | Formation process of germanium |
| US10777331B2 (en) | 2016-11-11 | 2020-09-15 | Curium Us Llc | Processes for generating germanium-68 with reduced volatiles |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2056471A (en) * | 1979-08-14 | 1981-03-18 | Deutsches Krebsforsch | Ion-exchanger for Separating Gallium-68 from its Parent Nuclide Germanium-68 |
| US4288424A (en) * | 1979-01-15 | 1981-09-08 | Massachusetts Institute Of Technology | Generator for ionic gallium-68 based on column chromatography |
-
2005
- 2005-03-08 WO PCT/IB2005/050843 patent/WO2005089912A1/en not_active Ceased
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4288424A (en) * | 1979-01-15 | 1981-09-08 | Massachusetts Institute Of Technology | Generator for ionic gallium-68 based on column chromatography |
| GB2056471A (en) * | 1979-08-14 | 1981-03-18 | Deutsches Krebsforsch | Ion-exchanger for Separating Gallium-68 from its Parent Nuclide Germanium-68 |
Cited By (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| RU2331439C1 (en) * | 2007-03-22 | 2008-08-20 | Закрытое акционерное общество "Циклотрон" | Method of obtaining radionuclide generator of gallium-68 |
| DE102009007799A1 (en) * | 2009-02-06 | 2010-08-26 | ITM Isotopen Technologien München AG | Molecule for the functionalization of a carrier, binding of a radionuclide to the carrier and radionuclide generator for the production of the radionuclide and production method |
| DE102009007799B4 (en) * | 2009-02-06 | 2010-10-14 | ITM Isotopen Technologien München AG | Molecule for the functionalization of a carrier, binding of a radionuclide to the carrier and radionuclide generator for the production of the radionuclide and production method |
| US9142328B2 (en) | 2009-02-06 | 2015-09-22 | ITM Isotopen Technologien München AG | Molecule for functionalizing a support, attachment of a radionuclide to the support and radionuclide generator for preparing the radionuclide, and preparation process |
| US9802969B2 (en) | 2009-02-06 | 2017-10-31 | Itm Isotopen Technologien Munchen Ag | Molecule for functionalizing a support, attachment of a radionuclide to the support and radionuclide generator for preparing the radionuclide, and preparation process |
| CN101593567B (en) * | 2009-06-18 | 2011-10-26 | 天津赛德生物制药有限公司 | Preparation method of 68Ge sealed radioactive source |
| WO2011033120A3 (en) * | 2009-09-21 | 2011-11-03 | Ge Healthcare Limited | Method for obtaining 68ga |
| US20120178902A1 (en) * | 2009-09-21 | 2012-07-12 | Johan Ulin | Method for obtaining 68ga |
| US8663597B2 (en) | 2009-09-21 | 2014-03-04 | Ge Healthcare Limited | Method for obtaining 68Ga |
| JP2019060893A (en) * | 2013-06-27 | 2019-04-18 | キュリウム ユーエス エルエルシー | Formation process of germanium |
| US10777331B2 (en) | 2016-11-11 | 2020-09-15 | Curium Us Llc | Processes for generating germanium-68 with reduced volatiles |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Guhlke et al. | Simple new method for effective concentration of 188Re solutions from alumina-based 188W—188Re Generator | |
| AU2004228745B2 (en) | Method of obtaining gallium-68 and use thereof and device for carrying out said method | |
| US20030194364A1 (en) | Multicolumn selectivity inversion generator for production of high purity actinium for use in therapeutic nuclear medicine | |
| US5409677A (en) | Process for separating a radionuclide from solution | |
| US9790097B2 (en) | Purification of 68Ge/68Ga generator eluate from Fe(III) intended to improve specific radioactivity of 68Ga-based radiopharmaceuticals | |
| EP3503929B1 (en) | Rapid isolation of cyclotron-produced gallium-68 | |
| AU2019399674B2 (en) | Processes and systems for producing and/or purifying gallium-68 | |
| US8663597B2 (en) | Method for obtaining 68Ga | |
| WO2005089912A1 (en) | Gallium-68 | |
| US4330507A (en) | Method and system for generating and collecting gallium-68 using alkaline eluant | |
| KR20210064241A (en) | Method for producing lead-212 from an aqueous solution containing thorium-228 and its daughters | |
| WO2007103277A2 (en) | Separation of germanium-68 from gallium-68 | |
| RU2768732C2 (en) | Method of producing isotope | |
| Betenekov et al. | Prospects for the Development of an 225Ac/213Bi Generator Using Inorganic Hydroxide Sorbents | |
| US8932876B2 (en) | Method and system for purifying charged radioisotopes | |
| Pao et al. | A new method for the preparation of68Ga-generators following proton bombardment of gallium oxide targets | |
| US10562835B1 (en) | Method for producing thorium-226 | |
| Fonseca et al. | GMP-automated purification of copper-61 produced in cyclotron liquid targets: Methodological aspects | |
| RU2522892C1 (en) | Method of obtaining active pharmaceutical substance for synthesis of gallium-68 preparations | |
| EP1146953B1 (en) | Process for the purification and concentration of radioiodide isotopes | |
| CN115029566B (en) | A method for separating zirconium from yttrium samples using TEVA-UTEVA resin | |
| JP2022138042A (en) | Method for producing target nuclide | |
| ES2928590T3 (en) | Methods to purify molybdenum-99 | |
| HK1260173A1 (en) | Isotope preparation method | |
| Fassbender et al. | Bulk processing of radionuclide generator parents at the Los Alamos Hot Cell Facility |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| AK | Designated states |
Kind code of ref document: A1 Designated state(s): AE AG AL AM AT AU AZ BA BB BG BR BW BY BZ CA CH CN CO CR CU CZ DE DK DM DZ EC EE EG ES FI GB GD GE GH GM HR HU ID IL IN IS JP KE KG KP KR KZ LC LK LR LS LT LU LV MA MD MG MK MN MW MX MZ NA NI NO NZ OM PG PH PL PT RO RU SC SD SE SG SK SL SM SY TJ TM TN TR TT TZ UA UG US UZ VC VN YU ZA ZM ZW |
|
| AL | Designated countries for regional patents |
Kind code of ref document: A1 Designated state(s): GM KE LS MW MZ NA SD SL SZ TZ UG ZM ZW AM AZ BY KG KZ MD RU TJ TM AT BE BG CH CY CZ DE DK EE ES FI FR GB GR HU IE IS IT LT LU MC NL PL PT RO SE SI SK TR BF BJ CF CG CI CM GA GN GQ GW ML MR NE SN TD TG |
|
| 121 | Ep: the epo has been informed by wipo that ep was designated in this application | ||
| NENP | Non-entry into the national phase |
Ref country code: DE |
|
| WWW | Wipo information: withdrawn in national office |
Country of ref document: DE |
|
| 122 | Ep: pct application non-entry in european phase |