| 序号 | 专利名 | 申请号 | 申请日 | 公开（公告）号 | 公开（公告）日 | 发明人 |
|---|---|---|---|---|---|---|
| 1 | 从辐照的226Ra-目标物中提纯225Ac的工艺 | CN200780006072.5 | 2007-02-19 | CN101390171B | 2013-02-13 | 约苏埃·曼纽尔·莫雷诺·贝穆德斯; 安德里亚·特勒; 理查德·亨克尔曼; 伊娃·卡巴伊; 恩斯特·欣格斯 |
| 本发明描述了一种从支撑物上的辐照的226Ra-目标物中提纯225Ac的工艺，该工艺包括对226Ra-目标物进行淋洗处理，其利用硝酸或盐酸浸出基本上所有的225Ac和226Ra，接着进行第一萃取层析，用于从226Ra和其他Ra同位素中分离225Ac，和第二萃取层析，用于从210Po和210Pb中分离225Ac。最终纯化的225Ac可用于制备制药用的组合物。 | ||||||
| 2 | 从辐照的226Ra-目标物中提纯225Ac的工艺 | CN200780006072.5 | 2007-02-19 | CN101390171A | 2009-03-18 | 约苏埃·曼纽尔·莫雷诺·贝穆德斯; 安德里亚·特勒; 理查德·亨克尔曼; 伊娃·卡巴伊; 恩斯特·欣格斯 |
| 本发明描述了一种从支撑物上的辐照的226Ra－目标物中提纯225Ac的工艺，该工艺包括对226Ra－目标物进行淋洗处理，其利用硝酸或盐酸浸出基本上所有的225Ac和226Ra，接着进行第一萃取层析，用于从226Ra和其他Ra同位素中分离225Ac，和第二萃取层析，用于从210Po和210Pb中分离225Ac。最终纯化的225Ac可用于制备制药用的组合物。 | ||||||
| 3 | ２２３Ｒａ組成物中の２２７Ａｃの定量化方法 | JP2016533836 | 2014-08-13 | JP2016536593A | 2016-11-24 | グロ・エリザベス・イェルム |
| 組成物を第1の固相抽出カラムAに通過させるステップであって、前記カラムはトリウム特異的樹脂を含むステップと、カラムAの溶出液を第2の固相抽出カラムBに通過させるステップであって、前記カラムはアクチニウム特異的樹脂を含むステップと、カラムBの樹脂上に吸収された227Acを回収し、その量を測定するステップとを含む223Ra組成物中の227Acの定量化方法。 | ||||||
| 4 | Verfahren zur Erzeugung von Actinium-225 | EP96110720.8 | 1996-07-03 | EP0752709B1 | 1999-03-24 | Koch, Lothar; Fuger, Jean; van Geel, Jacques |
| 5 | METHOD FOR THE QUANTIFICATION OF 227AC IN 223RA COMPOSITIONS | EP14752275.9 | 2014-08-13 | EP3033156A1 | 2016-06-22 | HJELLUM, Gro Elisabeth |
| A method for the quantification of 227Ac in a 223Ra composition comprising passing the composition through a first solid phase extraction column A, wherein said column comprises a thorium specific resin, passing the eluate of column A through a second solid phase extraction column B, wherein said column comprises an actinium specific resin and recovering the 227Ac absorbed onto the resin in column B and determining the amount thereof. | ||||||
| 6 | Method for the quantification of 227AC in 223RA compositions | US14912312 | 2014-08-13 | US09874550B2 | 2018-01-23 | Gro Elisabeth Hjellum |
| A method for the quantification of 227Ac in a 223Ra composition comprising passing the composition through a first solid phase extraction column A, wherein said column comprises a thorium specific resin, passing the eluate of column A through a second solid phase extraction column B, wherein said column comprises an actinium specific resin and recovering the 227Ac absorbed onto the resin in column B and determining the amount thereof. | ||||||
| 7 | Method for purification of 225AC from irradiated 226RA-targets | US14231354 | 2014-03-31 | US09534277B1 | 2017-01-03 | Josue Manuel Moreno Bermudez; Andreas Turler; Richard Henkelmann; Eva Kabai; Ernst Huenges |
| The present invention describes a method for purification of 225Ac from irradiated 226Ra-targets provided on a support, comprising a leaching treatment of the 226Ra-targets for leaching essentially the entirety of 225Ac and 226Ra with nitric or hydrochloric acid, followed by a first extraction chromatography for separating 225Ac from 226Ra and other Ra-isotops and a second extraction chromatography for separating 225Ac from 210Po and 210Pb. The finally purified 225Ac can be used to prepare compositions useful for pharmaceutical purposes. | ||||||
| 8 | Production of isotopes using high power proton beams | US13025079 | 2011-02-10 | US09202602B2 | 2015-12-01 | Jerry A. Nolen, Jr.; Itacil C. Gomes |
| The invention provides for a method for producing isotopes using a beam of particles from an accelerator, whereby the beam is maintained at between about 70 to 2000 MeV; and contacting a thorium-containing target with the particles. The medically important isotope 225Ac is produced via the nuclear reaction (p,2p6n), whereby an energetic proton causes the ejection of 2 protons and 6 neutrons from a 232Th target nucleus. Another medically important isotope 213Bi is then available as a decay product. The production of highly purified 211At is also provided. | ||||||
| 9 | METHOD FOR PRODUCING ACTINIUM-225 AND ISOTOPES OF RADIUM AND TARGET FOR IMPLEMENTING SAME | US13120186 | 2009-09-09 | US20110317795A1 | 2011-12-29 | Boris Leonidovich Zhuikov; Stepan Nikolaevich Kalmykov; Ramiz Avtandilovich Aliev; Stanislav Viktorovich Ermolaev; Vladimir Mikhailovich Kokhanyuk; Nikolai Alexandrovich Konyakhin; Ivan Gundarovich Tananaev; Boris Fedorovich Myasoedov |
| The invention relates to the field of nuclear technology and radiochemistry, more specifically to the production and isolation of radionuclides for medical purposes. The method for producing actinium-225 and isotopes of radium comprises irradiating a solid block of metallic thorium of a thickness of 2 to 30 mm, which is contained within a hermetically sealed casing made of a material which does not react with thorium, with a flow of accelerated charged particles with high intensity. The irradiated metallic thorium is removed from the casing and is either heated with the addition of lanthanum and the distillation of radium or is dissolved in nitric acid with the recovery of actinium-225 by extraction. A target for implementing this method consists of blocks of metallic thorium of a thickness of 2 to 30 mm, which are contained within a hermetically scaled casing made of different materials which do not react with thorium. | ||||||
| 10 | Multicolumn selectivity inversion generator for production of high purity actinium for use in therapeutic nuclear medicine | US10261031 | 2002-09-30 | US07087206B2 | 2006-08-08 | Andrew H. Bond; E. Philip Horwitz; Daniel R. McAlister |
| A multicolumn selectivity inversion generator separation method has been developed in which actinium ions, a desired daughter radionuclide, are selectively extracted from a solution of the thorium parent and daughter radionuclides by a primary separation column, stripped, and passed through a second guard column that retains any parent or other daughter interferents, while the desired daughter actinium ions and radium ions elute. This separation method minimizes the effects of radiation damage to the separation material and permits the reliable production of radionuclides of high chemical and radionuclidic purity for use in diagnostic or therapeutic nuclear medicine. | ||||||
| 11 | Method for purifying 225Ac from irradiated 226Ra target | JP2008554697 | 2007-02-19 | JP5145545B2 | 2013-02-20 | ベルムデス ジョシュ マヌエル モレノ; アンドレアス テューラー; リヒャルト ヘンケルマン; エヴァ カバイ; エルンスト ヒュエンゲス |
| A method for purifying 225>Ac (I) from irradiated 226>Ra (II) targets involves eluting all the (I) and (II) with acid, separating (I) from (II) and other radium isotopes by extraction chromatography using a solid support coated with N,N-dialkylamidomethyl-diorganophosphine oxide in a trialkyl phosphate, and then separating (I) from 210>Po and 210>Pb by extraction chromatography on a solid support coated with optionally substituted bis-cyclohexano-18-crown-6 in a 4-12C alkanol.. A method (M1) for purifying 225>Ac from irradiated 226>Ra targets (made on a support) involves (a) eluting the target with nitric or hydrochloric acid under reflux to remove all the 225>Ac and 226>Ra, (b) removing the HCl (if used) and redissolving the material in nitric acid, (c) concentrating the extract, (d) separating the 225>Ac from 226>Ra and other radium isotopes by extraction chromatography using a solid support coated with an extraction system comprising compound(s) of formula (I) in compound(s) of formula (II), (e) eluting the retained 225>Ac from the stationary phase with dilute nitric or hydrochloric acid ( 226>Ra is eluted in stage (d)), (f) separating the 225>Ac from 210>Po and 210>Pb by extraction chromatography using a solid support coated with an extraction system comprising compound(s) of formula (III) in compound(s) of formula R 10>-OH (IV), (g) using 2M-HCl as mobile phase and (h) recovering 225>Ac from the eluate, the 210>Po and 210>Pb being retained on the solid support. R1, R2 : octyl, n-octyl, phenyl or (1-3C alkyl)-substituted phenyl; R3, R4 : n- or iso-propyl, or n- or iso-butyl; R5-R7 : 2-5C alkyl, preferably n- or iso-butyl; R8, R9 : H, 1-5C alkyl or tert.-butyl; R10 : 4-12C alkyl. Independent claims are included for (1) a method (M2) for purifying 225>Ac as above, in which the solid support in stage (d) is coated with compound(s) of formula (IA) and stage (e) involves elution with 0.3-0.01M nitric acid or 1-0.05M hydrochloric acid (2) a method (M3) as above in which the support in (d) is coated with compound(s) of formula (IB) and stage (e) involves elution with 0.02-0.1M nitric acid (3) pharmaceutically-acceptable radionuclide compositions containing 225>Ac and obtained by the above methods. R1a-R4a : octyl or 2-ethylhexyl. ACTIVITY : Cytostatic. No biological data given. MECHANISM OF ACTION : None given. | ||||||
| 12 | Method for purifying 225Ac from irradiated 226Ra target | JP2008554697 | 2007-02-19 | JP2009527731A | 2009-07-30 | エヴァ カバイ; アンドレアス テューラー; エルンスト ヒュエンゲス; リヒャルト ヘンケルマン; ベルムデス ジョシュ マヌエル モレノ |
| 本発明は、支持体上に設けられる放射線照射
２２６ Ｒａ標的から
２２５ Ａｃを精製する方法を記載しており、当該方法は、硝酸又は塩酸を用いて
２２５ Ａｃ及び
２２６ Ｒａを完全な形態で本質的に溶出させる
２２６ Ｒａ標的の溶出処理と、続いて
２２６ Ｒａ及び他のＲａ同位体から
２２５ Ａｃを分離させる第１の抽出クロマトグラフィと、
２１０ Ｐｏ及び
２１０ Ｐｂから
２２５ Ａｃを分離させる第２の抽出クロマトグラフィとを含む。 最後的に精製された
２２５ Ａｃは、医薬用途に有用な組成物を調製するのに用いることができる。
【選択図】図３ｂ |
||||||
| 13 | Method for purification of 225AC from irradiated 226RA-targets | US15359053 | 2016-11-22 | US09790573B2 | 2017-10-17 | Josue Manuel Moreno Bermudez; Andreas Turler; Richard Henkelmann; Eva Kabai; Ernst Huenges |
| The present invention describes a method for purification of 225Ac from irradiated 226Ra-targets provided on a support comprising a leaching treatment of the 225Ra-targets for leaching essentially for the entirety of 223Ac and 226Ra with nitric or hydrochloric acid, followed by a first extraction chromatography for separating 225Ac from 226Ra and other Ra-isotops and a second extraction chromotography for separating 225Ac from 210Po and 210Pb. The finally purified 225Ac can be used to prepare compositions useful for pharmaceutical purposes. | ||||||
| 14 | METHOD FOR THE QUANTIFICATION OF 227AC IN 223RA COMPOSITIONS | US14912312 | 2014-08-13 | US20160209387A1 | 2016-07-21 | Gro Elisabeth HJELLUM |
| A method for the quantification of 227Ac in a 223Ra composition comprising passing the composition through a first solid phase extraction column A, wherein said column comprises a thorium specific resin, passing the eluate of column A through a second solid phase extraction column B, wherein said column comprises an actinium specific resin and recovering the 227Ac absorbed onto the resin in column B and determining the amount thereof. | ||||||
| 15 | PRODUCTION OF ISOTOPES USING HIGH POWER PROTON BEAMS | US13025079 | 2011-02-10 | US20110200154A1 | 2011-08-18 | Jerry A. Nolen, JR.; Itacil C. Gomes |
| The invention provides for a method for producing isotopes using a beam of particles from an accelerator, whereby the beam is maintained at between about 70 to 2000 MeV; and contacting a thorium-containing target with the particles. The medically important isotope 225Ac is produced via the nuclear reaction (p,2p6n), whereby an energetic proton causes the ejection of 2 protons and 6 neutrons from a 232Th target nucleus. Another medically important isotope 213Bi is then available as a decay product. The production of highly purified 211At is also provided. | ||||||
| 16 | MULTIVALENT METAL ION EXTRACTION USING DIGLYCOLAMIDE-COATED PARTICLES | US11619026 | 2007-01-02 | US20070131618A1 | 2007-06-14 | E. Horwitz; Richard Barrans; Andrew Bond |
| A separation medium, a method for using that separation medium and an apparatus for selectively extracting multivalent cations such as pseudo-lanthanide, prelanthanide, lanthanide, preactinide or actinide cations from an aqueous acidic sample solution is described. The separation medium is preferably free-flowing and comprises particles having a diglycolamide (DGA) extractant dispersed onto an inert, porous support. | ||||||
| 17 | Multivalent metal ion extraction using diglycolamide-coated particles | US10351717 | 2003-01-27 | US07157022B2 | 2007-01-02 | E. Philip Horwitz; Richard E. Barrans, Jr.; Andrew H. Bond |
| A separation medium, a method for using that separation medium and an apparatus for selectively extracting multivalent cations such as pseudo-lanthanide, prelanthanide, lanthanide, preactinide or actinide cations from an aqueous acidic sample solution is described. The separation medium is preferably free-flowing and comprises particles having a diglycolamide (DGA) extractant dispersed onto an inert, porous support. | ||||||
| 18 | Multivalent metal ion extraction using diglycolamide-coated particles | US10351717 | 2003-01-27 | US20040062695A1 | 2004-04-01 | E. Philip Horwitz; Richard E. Barrans JR.; Andrew H. Bond |
| A separation medium, a method for using that separation medium and an apparatus for selectively extracting multivalent cations such as pseudo-lanthanide, prelanthanide, lanthanide, preactinide or actinide cations from an aqueous acidic sample solution is described. The separation medium is preferably free-flowing and comprises particles having a diglycolamide (DGA) extractant dispersed onto an inert, porous support. | ||||||
| 19 | Multicolumn selectivity inversion generator for production of high purity actinium for use in therapeutic nuclear medicine | US10261031 | 2002-09-30 | US20030194364A1 | 2003-10-16 | Andrew H. Bond; E. Philip Horwitz; Daniel R. McAlister |
| A multicolumn selectivity inversion generator separation method has been developed in which actinium ions, a desired daughter radionuclide, are selectively extracted from a solution of the thorium parent and daughter radionuclides by a primary separation column, stripped, and passed through a second guard column that retains any parent or other daughter interferents, while the desired daughter actinium ions and radium ions elute. This separation method minimizes the effects of radiation damage to the separation material and permits the reliable production of radionuclides of high chemical and radionuclidic purity for use in diagnostic or therapeutic nuclear medicine. | ||||||
| 20 | METHOD FOR PURIFICATION OF 225AC FROM IRRADIATED 226RA-TARGETS | EP07711580.6 | 2007-02-19 | EP1987522B1 | 2010-07-14 | MORENO BERMUDEZ, Josue, Manuel; TÜRLER, Andreas; HENKELMANN, Richard; KABAI, Eva; HÜENGES, Ernst |
| A method for purifying 225>Ac (I) from irradiated 226>Ra (II) targets involves eluting all the (I) and (II) with acid, separating (I) from (II) and other radium isotopes by extraction chromatography using a solid support coated with N,N-dialkylamidomethyl-diorganophosphine oxide in a trialkyl phosphate, and then separating (I) from 210>Po and 210>Pb by extraction chromatography on a solid support coated with optionally substituted bis-cyclohexano-18-crown-6 in a 4-12C alkanol.. A method (M1) for purifying 225>Ac from irradiated 226>Ra targets (made on a support) involves (a) eluting the target with nitric or hydrochloric acid under reflux to remove all the 225>Ac and 226>Ra, (b) removing the HCl (if used) and redissolving the material in nitric acid, (c) concentrating the extract, (d) separating the 225>Ac from 226>Ra and other radium isotopes by extraction chromatography using a solid support coated with an extraction system comprising compound(s) of formula (I) in compound(s) of formula (II), (e) eluting the retained 225>Ac from the stationary phase with dilute nitric or hydrochloric acid ( 226>Ra is eluted in stage (d)), (f) separating the 225>Ac from 210>Po and 210>Pb by extraction chromatography using a solid support coated with an extraction system comprising compound(s) of formula (III) in compound(s) of formula R 10>-OH (IV), (g) using 2M-HCl as mobile phase and (h) recovering 225>Ac from the eluate, the 210>Po and 210>Pb being retained on the solid support. R1, R2 : octyl, n-octyl, phenyl or (1-3C alkyl)-substituted phenyl; R3, R4 : n- or iso-propyl, or n- or iso-butyl; R5-R7 : 2-5C alkyl, preferably n- or iso-butyl; R8, R9 : H, 1-5C alkyl or tert.-butyl; R10 : 4-12C alkyl. Independent claims are included for (1) a method (M2) for purifying 225>Ac as above, in which the solid support in stage (d) is coated with compound(s) of formula (IA) and stage (e) involves elution with 0.3-0.01M nitric acid or 1-0.05M hydrochloric acid (2) a method (M3) as above in which the support in (d) is coated with compound(s) of formula (IB) and stage (e) involves elution with 0.02-0.1M nitric acid (3) pharmaceutically-acceptable radionuclide compositions containing 225>Ac and obtained by the above methods. R1a-R4a : octyl or 2-ethylhexyl. ACTIVITY : Cytostatic. No biological data given. MECHANISM OF ACTION : None given. | ||||||
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