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WO2002099816A2 - Traitement d'une cible - Google Patents

Traitement d'une cible Download PDF

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Publication number
WO2002099816A2
WO2002099816A2 PCT/US2002/017678 US0217678W WO02099816A2 WO 2002099816 A2 WO2002099816 A2 WO 2002099816A2 US 0217678 W US0217678 W US 0217678W WO 02099816 A2 WO02099816 A2 WO 02099816A2
Authority
WO
WIPO (PCT)
Prior art keywords
target
sonication
dissolution medium
radioisotope
irradiated target
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
Application number
PCT/US2002/017678
Other languages
English (en)
Other versions
WO2002099816A3 (fr
Inventor
Hirohiko Yamauchi
Toshiyuki Yoshioka
Noboru Minamiguchi
Shintarou Ogata
Michael Drobnik
Gerald Wilgus
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.)
Nihon Medi Physics Co Ltd
Medi Physics Inc
Original Assignee
Nihon Medi Physics Co Ltd
Medi Physics Inc
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 Nihon Medi Physics Co Ltd, Medi Physics Inc filed Critical Nihon Medi Physics Co Ltd
Priority to AU2002310305A priority Critical patent/AU2002310305B2/en
Priority to JP2003502839A priority patent/JP4231779B2/ja
Priority to KR1020037015876A priority patent/KR100858265B1/ko
Publication of WO2002099816A2 publication Critical patent/WO2002099816A2/fr
Publication of WO2002099816A3 publication Critical patent/WO2002099816A3/fr
Anticipated expiration legal-status Critical
Ceased legal-status Critical Current

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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
    • G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
    • G21G1/04—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes outside nuclear reactors or particle accelerators
    • G21G1/10—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes outside nuclear reactors or particle accelerators by bombardment with electrically charged particles

Definitions

  • the present invention relates to an improved process for the recovery of a radioisotope from an irradiated target, such as a target from a cyclotron.
  • the improvement comprises sonication of the target dissolution medium.
  • radioisotopes by bombardment of a non-radioactive target with particles, especially protons in a cyclotron, to convert a small percentage of the irradiated target surface into one or more radioisotopes.
  • the radioisotope is then separated from the target by either:
  • the dissolution medium is subjected to further purification steps involving one or more selective separation techniques such as ion exchange chromatography, solvent extraction or precipitation.
  • Method (ii) may employ controlled conditions such as limited concentrations or amounts of chemicals, or solvents in which only the target surface has significant solubility.
  • Method (ii) is preferred where the target is relatively precious, eg. an artificially enriched level of a particular isotope to improve the yield of the desired radioisotope product, or the target comprises a precious metal.
  • Method (ii) also has the advantage that there are lower levels of the non-radioactive target material present in solution. This makes the subsequent separation and purification of the radioisotope more straightforward.
  • radioisotope is to be used for medical applications involving administration to the human body (ie. a radiopharmaceutical), where removal of the potentially toxic levels of the non-radioactive target material (typically a heavy metal) is highly desirable.
  • a radiopharmaceutical ie. a radiopharmaceutical
  • removal of the potentially toxic levels of the non-radioactive target material typically a heavy metal
  • carrier-free 67 Cu can be produced by proton spallation of a zinc oxide target with subsequent chemical separation and purification.
  • the zinc oxide target is irradiated with protons having an energy of 800 MeV, and the irradiated target dissolved in concentrated acid.
  • the 67 Cu is then separated by a series of ion exchange chromatography and precipitation procedures.
  • US 3993538 discloses that 201 T1 suitable for use as a myocardial imaging radiopharmaceutical can be prepared by bombardment of a thallium target with 20-30
  • MeV protons via the reaction Pb radioisotope formed has a half- life of 9.4 hours, and decays to the desired 201 T1.
  • the target is completely dissolved in concentrated nitric acid forming soluble lead and thallium nitrates. Evaporation and further chemical purification steps gave the desired 201 T1 product.
  • US 4297166 discloses a thallium target for the production of the radioisotope 201 T1, in which the 203 T1 target material is electroplated onto an electroconductive support such as copper or silver.
  • the electroconductive support has two advantages. First, it can be used to provide efficient cooling of the thallium layer (via a circulating fluid such as water or gas). Second, it can facilitate target processing, since only the thallium target layer and radioisotope formed is dissolved during processing. This makes the purification of the 201 T1 radioisotope more straightforward, since the processed target solution does not contain substantial amounts of the non-radioactive electroconductive support (eg. copper). After chemical processing, the target electroconductive support can then simply be reused by electroplating with more thallium, and subsequent proton bombardment.
  • the non-radioactive electroconductive support eg. copper
  • JP 04-326096 A (1992) discloses a cyclotron target which comprises silver plated onto a copper support.
  • the desired target material ( 68 Zn) is plated onto the silver, and then irradiated with a proton beam.
  • the silver layer means that no copper is present in the acid processing solutions, ie. the recovery and purification of the desired 68 Zn radioisotope is simplified.
  • US 6011825 discloses a cyclotron method for the production of radioisotopes, especially 64 Cu.
  • the 64 Cu is produced by proton bombardment of a target which comprises 64 Ni deposited onto a gold substrate.
  • the irradiated 64 Ni together with the 64 Cu product are dissolved off the gold disk in 6.0 M hydrochloric acid at 90 °C.
  • Prior art chemistry used to process targets therefore typically employs concentrated solutions of mineral acids (eg. hydrochloric acid), or powerful oxidising agents such as hydrogen peroxide. Acids which are also powerful oxidising agents, such as concentrated nitric acid may also be used. Heating is often also applied. Such forcing conditions are understandable given that the target material to be dissolved may be a relatively unreactive metal such as rhodium.
  • the difficulty of achieving the required dissolution of the target may also mean that extended contact times are required.
  • all such target processing time is time during which radioactive decay of the desired product is occurring, ie. product is being lost.
  • the present invention provides a process for the separation of a radioisotope from an irradiated target comprising:
  • the target of the present invention suitably comprises a 'surface solid material' which, when irradiated with charged particles reacts to give one or more radioisotopes.
  • the surface solid material is thus that part of the irradiated target which reacts during the irradiation to give the desired radioisotope product.
  • the charged particles are suitably derived from an accelerator, preferably a cyclotron.
  • the charged particles may be protons, deuterons, alpha, 3 He or electrons, and are preferably protons.
  • Suitable surface solid materials include metals such as thallium, cadmium, rhodium, molybdenum or zinc, or metal oxides such as zinc oxide, strontium oxide or gallium oxide, plus such materials containing an artificially enriched level of a particular isotope.
  • Preferred surface solid materials are those which are suitable for plating (eg. by electroplating or electroless deposition) onto a support material.
  • the target preferably comprises a 'support material' onto which is provided an outer coating of the surface solid material to be irradiated.
  • the support material functions to provide effective cooling of the irradiated surface solid material during the irradiation, and permits separation of the radioisotope product, leaving the support material substantially unchanged, ready to be reused.
  • the 'support material' preferably comprises a material which is a good conductor of heat and/or electricity, ie. is electroconductive. Suitable support materials include copper, silver, aluminium, stainless steel or carbon (eg. graphite).
  • the support material is suitably of a shape and size that permits facile production, as well as ease of attachment and detachment from the target assembly.
  • a preferred shape of the support material is a plate.
  • the support material preferably comprises silver, and is most preferably made entirely of silver, since silver has advantages over copper.
  • the non-radioactive copper of a copper support material can dissolve in acidic dissolution media (especially nitric acid). This makes purification and isolation of the radioisotope more difficult, by eg. increasing the viscosity of the dissolution medium, making solvent extraction of the radioisotope product more difficult.
  • one advantage of the use of silver as the support material is that silver does not dissolve readily in nitric acid, which makes subsequent purification of the radioisotope easier.
  • Silver does, however, have a finite solubility in concentrated hydrobromic acid, hence is less advantageous when the dissolution medium comprises concentrated hydrobromic acid.
  • any protons which penetrate the surface solid material and are captured by the copper lead to the production of the potential impurity radioisotope 65 Zn.
  • At least a portion of any 65 Zn formed may dissolve in the dissolution medium, especially when the dissolution medium comprises aqueous acid, since Zn(0) dissolves in acid.
  • 65 Zn has a half-life of 244 days, and hence both the copper target support material and the dissolution medium are, in effect, contaminated for a prolonged period.
  • the period necessary to await radioactive decay of the 65 Zn is so long (minimum 10 half-lives), that corrosion of the copper support is likely to occur during the storage period to allow for decay.
  • any 65 Zn contamination of the dissolution medium means that, even after the desired radioisotope product has been isolated or extracted, the dissolution medium must be kept for prolonged periods to await decay of the 65 Zn.
  • the support material comprises silver
  • any protons captured by the silver generate the radioisotopes 105 Ag and 106m Ag, which have half-lives of 41.3 and 8.5 days respectively. The result is that such silver target supports can be reused after an appropriate decay period (suitably of approximately one year).
  • Radioisotopes which can be prepared using the present process include 201 T1, 83 Rb, 88 Y, 88 Zr, 96 Tc, 97 Ru, In, 67 Ga, 68 Ge, 57 Co, 103 Pd, 62 Cu and 67 Cu.
  • the process is especially useful for 201 T1, m In 3 67 Ga, 103 Pd, 57 Co and 62 Cu, particularly 201 T1.
  • the present invention may also be applied to the production of parent radioisotopes which decay to give positron emitters useful as radiopharmaceuticals, as used in so-called radioisotope generators.
  • Suitable parent radioisotopes include: 82 Sr ( 82 Rb), 68 Ge ( 68 Ga) and 62 Zn ( 62 Cu).
  • the support material may optionally further comprise an 'inert layer' at its' outer surface.
  • the inert layer suitably forms an unreactive layer interspersed between the surface solid material and the bulk of the support material.
  • the inert layer comprises a material which is essentially insoluble in the dissolution medium, and thus protects the support material from partial dissolution when the irradiated target is processed.
  • the inert layer is provided at a thickness of less than 10 ⁇ m, to maximise the transparency of the inert layer to the charged particles used in the target irradiation, and hence minimise potential radioisotopic impurities arising due to capture of the charged particles by the inert layer itself.
  • the inert layer functions to minimise dissolution of the target support material, together with any radioisotopic impurities formed via irradiation of the target support material (eg. the low energy gamma emitters 105 Ag or I06m Ag from a silver support material), into the dissolution medium. Any such dissolution could introduce potential impurities into the desired radioisotope product.
  • Suitable inert layers comprise unreactive metals such as silver, gold, platinum, tungsten, tantalum or nickel. When the surface solid material is zinc, and the support material is copper, then nickel represents a preferred inert layer material.
  • the inert layer comprises gold or silver, most preferably gold. Gold has the advantage that it has greater passivity (ie. is less reactive chemically), and is most suitable for accepting the plated solid material of the target.
  • the sonication of the present invention may suitably be provided either by an ultrasonic probe which is immersed in the dissolution medium, or via external sonication of the container or bath containing the dissolution medium.
  • Suitable sonication probes and sonication baths are commercially available.
  • the sonication apparatus converts the frequency of the power supply (eg. 50 to 60 Hz) to high frequency 20 kHz electrical energy. This high frequency electrical energy is in turn converted via a transducer in the sonication apparatus to mechanical vibrations (either of the sonication probe or sonication bath). The mechanical vibrations are intensified by the sonication apparatus, thus creating pressure waves within the dissolution medium. These pressure waves form microbubbles in the dissolution medium, which expand during the negative pressure phase, and implode violently during the positive pressure phase. This phenomenon is known as cavitation, and causes the molecules in the dissolution medium to become intensely agitated. Suitable sonication probes have a level of cavitation at the horn tip of ca.
  • suitable sonication baths may have a lower cavitation level of ca. 1 W/cm 2 at the horn tip, with a frequency of 36-42 kHz.
  • the sonication bath may comprise any material compatible with the dissolution medium, but is preferably Teflon .
  • Teflon a material compatible with the dissolution medium.
  • Tl it has been found that there are separation distance effects (see Examples 1 and 2).
  • the dissolution can be accelerated using an ultrasonic immersion probe, the irradiated 203 Tl-enriched target material in proximity to the probe was found to be dissolved smoothly, whereas those parts of the irradiated target more distant from the probe were harder to dissolve.
  • an immersion probe gives less uniform effects due to inhomogeneity, whereas ultrasonic baths give more uniform or homogeneous performance. It is therefore preferred that, when the size and geometry of the target is suitable for immersion of the whole target in a sonication bath, that such a sonication bath is used, ie. that external sonication of the dissolution medium is applied. External sonication also gives shorter dissolution times (see Example 1), and is more convenient since there is no need to wash or decontaminate the immersion probe between preparations. Internal sonication may, however, be the best option when the size and geometry of the target is such that only a portion of the target can be immersed in a sonication bath.
  • the shorter dissolution times of the present invention are believed to result from improved kinetics of mixing the dissolution medium with the surface solid material, due to the cavitation of the dissolution medium. This confers particular improvements where the solubility of the irradiated target material in the dissolution medium is low, especially when it is necessary to dissolve the whole irradiated target.
  • any reduction in the target processing time results in an improved yield, because there is reduced loss due to radioactive decay during target processing.
  • this problem is exacerbated the shorter the half-life of the radioisotope, such as positron emitters which may have half-lives of the order of a few hours. Shorter processing times also reduce the risk of radiation dose to the operator, by reducing the time spent in target processing.
  • the process of the present invention also permits the use of much milder conditions for processing the irradiated target. This includes the use of more dilute solutions of acids and/or oxidants, lower temperatures, and shorter reaction times.
  • dilute aqueous nitric can be used as the dissolution medium instead of the conventional concentrated nitric acid solution (7 molar).
  • 'dilute aqueous nitric acid' is meant an aqueous solution which is 0.5 to 1.5 molar; preferably 0.8 to 1.2 molar, most preferably about 1 molar.
  • the present invention provides an improved process for the production of 201 T1.
  • the improved process comprises the use of the sonication process as described above, together with a target which comprises 203 T1 as the surface solid material, where the target is irradiated with protons, and the dissolution medium is 'dilute nitric acid' as defined above.
  • the support material preferably comprises silver, and most preferably is made entirely of silver metal. The use of silver as the support medium has the advantages described above, and the sonication method provides a shorter processing time, which gives improved yields of 201 T1.
  • the radioisotope Tl illustrates an additional reason why shorter processing times are important. It is typically produced by proton beam irradiation of a 203 Tl-enriched solid target material, giving 201 Pb via a (p,3n) nuclear reaction, and subsequent extraction of the trace amount of 201 Pb produced.
  • the 201 Pb initial product decays to 201 T1 with a half-life of 9.4 hours. This means that the Pb must be chemically separated from the target Tl before the desired Tl can be obtained, since once the Tl decay product has formed, it is chemically identical to the 203 TI target material, and hence impossible to separate therefrom.
  • Example 1 Sonication of 203 T1 Targets (Comparative Example).
  • Three identical silver target plates ie. targets where solid silver is used as the support material, in the shape of a plate, without an inert layer
  • a dissolution medium of 5% aqueous nitric acid solution (molarity ca. 1M) in three separate baths.
  • the dissolution of the 203 Tl-thallium target material was carried out: (a) without sonication, (b) with a 100 W ultrasonic probe,
  • Example 2 Production of Tl Using a Silver-containing Target.
  • the target was irradiated for 8 hours with protons, using a proton beam of about 30 MeV.
  • the dissolution of the irradiated 203 Tl-enriched target material was carried out in an ultrasonic bath of 300 W sonication power, with 5% aqueous (ie. ca. 1M) nitric acid as the dissolution medium. The dissolution was complete in about 10 minutes. Hydrochloric acid was then added to the solution..
  • the separation of the 201 Pb radioisotope produced was achieved by solvent extraction of the irradiated 203 Tl-enriched target material using diisopropylether.
  • the method of the present invention saves ca. 0.8 hours.
  • the yield of radioactivity of 201 T1 obtained via this method was 21.9 GBq per target plate at 15 hr after the completion of the Pb separation.
  • a target plate made of copper as the support material, and having 203 Tl-enriched target material plated onto its' surface was attached to a target support assembly made of aluminium for 201 T1 preparation, and irradiated with protons as per Example 2.
  • the extraction of the irradiated 203 Tl-enriched target material was performed in the same way as Example 2; except that the separation sequence was as follows: (i) evaporation of the nitric acid,

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  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • General Chemical & Material Sciences (AREA)
  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Particle Accelerators (AREA)
  • Radiation-Therapy Devices (AREA)
  • Saccharide Compounds (AREA)
  • Medicines That Contain Protein Lipid Enzymes And Other Medicines (AREA)

Abstract

La présente invention concerne un traitement amélioré permettant de récupérer un radio-isotope à partir d'une cible irradiée qui comprend un matériau superficiel solide. L'amélioration du procédé réside dans le fait qu'il comprend la sonication du milieu de dissolution de la cible, à savoir soit une sonication externe (par exemple à l'aide d'un bain de sonication), soit une sonication interne (par exemple, à l'aide d'une sonde de sonication immergée dans le milieu de dissolution). Ce procédé permet une récupération plus rapide et plus efficace du radio-isotope, cela dans des conditions plus douces.
PCT/US2002/017678 2001-06-05 2002-06-04 Traitement d'une cible Ceased WO2002099816A2 (fr)

Priority Applications (3)

Application Number Priority Date Filing Date Title
AU2002310305A AU2002310305B2 (en) 2001-06-05 2002-06-04 Process for the recovery of a radioisotope from an irradiated target
JP2003502839A JP4231779B2 (ja) 2001-06-05 2002-06-04 ターゲット処理
KR1020037015876A KR100858265B1 (ko) 2001-06-05 2002-06-04 피조사 표적으로부터의 방사성 동위원소 회수 방법

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US29598001P 2001-06-05 2001-06-05
US60/295,980 2001-06-05

Publications (2)

Publication Number Publication Date
WO2002099816A2 true WO2002099816A2 (fr) 2002-12-12
WO2002099816A3 WO2002099816A3 (fr) 2003-05-08

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PCT/US2002/017678 Ceased WO2002099816A2 (fr) 2001-06-05 2002-06-04 Traitement d'une cible

Country Status (5)

Country Link
JP (1) JP4231779B2 (fr)
KR (1) KR100858265B1 (fr)
CN (1) CN1264170C (fr)
AU (1) AU2002310305B2 (fr)
WO (1) WO2002099816A2 (fr)

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2019023787A1 (fr) * 2017-07-31 2019-02-07 Stefan Zeisler Système, appareil et procédé de production de radio-isotopes de gallium sur des accélérateurs de particules au moyen de cibles solides et composition de ga-68 produite selon le procédé
IT201700102990A1 (it) * 2017-09-14 2019-03-14 Istituto Naz Fisica Nucleare Metodo per l’ottenimento di un target solido per la produzione di radiofarmaci
US20210120661A1 (en) * 2017-06-09 2021-04-22 Kaneka Corporation Target for proton-beam or neutron-beam irradiation and method for generating radioactive substance using same
US11177116B2 (en) 2016-04-28 2021-11-16 Kaneka Corporation Beam intensity converting film, and method of manufacturing beam intensity converting film
US11239003B2 (en) 2016-04-21 2022-02-01 Kaneka Corporation Support substrate for radioisotope production, target plate for radioisotope production, and production method for support substrate
EP3940718A4 (fr) * 2019-03-11 2022-12-21 Kyoto Medical Technology Co., Ltd Système d'isolement de technétium 99m et procédé d'isolement de technétium 99m
EP4091178A4 (fr) * 2020-01-17 2024-09-04 BWXT Medical Ltd. Système et procédé pour la production d'isotopes du germanium-68

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP4571109B2 (ja) * 2006-09-12 2010-10-27 行政院原子能委員会核能研究所 放射性同位元素タリウム−２０１の製造工程
JP4674727B2 (ja) * 2006-10-27 2011-04-20 行政院原子能委員会核能研究所 放射性同位元素タリウム−２０１の分離装置
EP2131369A1 (fr) * 2008-06-06 2009-12-09 Technische Universiteit Delft Procédé de production de 99-Mo sans support ajouté
WO2014210352A1 (fr) * 2013-06-27 2014-12-31 Mallinckrodt Plc Procédé de production de germanium
CN113574613B (zh) * 2019-03-28 2024-11-29 住友重机械工业株式会社 靶照射系统及来自固体靶的放射性同位素的回收方法
US12315649B2 (en) 2020-09-03 2025-05-27 Curium Us Llc Purification process for the preparation of non-carrier added copper-64
CA3192205A1 (fr) * 2020-09-03 2022-03-10 Curium Us Llc Procede de purification pour la preparation de cuivre 64 sans vecteur ajoute

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Publication number Priority date Publication date Assignee Title
NL103068C (fr) * 1956-10-04
JPS54111100A (en) * 1978-02-20 1979-08-31 Nihon Mediphysics Co Ltd Method of making thallium target for irradiation in cyclotron
BE904936A (nl) * 1986-06-17 1986-10-16 Lemmens Godfried Werkwijze voor de decontaminatie van radioaktief besmette materialen.
JPH02206800A (ja) * 1989-02-07 1990-08-16 Power Reactor & Nuclear Fuel Dev Corp 塔槽類の除染方法

Cited By (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US11239003B2 (en) 2016-04-21 2022-02-01 Kaneka Corporation Support substrate for radioisotope production, target plate for radioisotope production, and production method for support substrate
US11177116B2 (en) 2016-04-28 2021-11-16 Kaneka Corporation Beam intensity converting film, and method of manufacturing beam intensity converting film
US20210120661A1 (en) * 2017-06-09 2021-04-22 Kaneka Corporation Target for proton-beam or neutron-beam irradiation and method for generating radioactive substance using same
WO2019023787A1 (fr) * 2017-07-31 2019-02-07 Stefan Zeisler Système, appareil et procédé de production de radio-isotopes de gallium sur des accélérateurs de particules au moyen de cibles solides et composition de ga-68 produite selon le procédé
EP3662728A4 (fr) * 2017-07-31 2021-08-18 Stefan Zeisler Système, appareil et procédé de production de radio-isotopes de gallium sur des accélérateurs de particules au moyen de cibles solides et composition de ga-68 produite selon le procédé
EP4389155A3 (fr) * 2017-07-31 2024-11-13 Triumf Inc. Système, appareil et procédé de production de radio-isotopes de gallium sur des accélérateurs de particules à l'aide de cibles solides et composition de ga-68 produite par ceux-ci
IT201700102990A1 (it) * 2017-09-14 2019-03-14 Istituto Naz Fisica Nucleare Metodo per l’ottenimento di un target solido per la produzione di radiofarmaci
WO2019053570A1 (fr) * 2017-09-14 2019-03-21 Istituto Nazionale Di Fisica Nucleare Procédé d'obtention d'une cible solide pour la production de produits radiopharmaceutiques
EP3940718A4 (fr) * 2019-03-11 2022-12-21 Kyoto Medical Technology Co., Ltd Système d'isolement de technétium 99m et procédé d'isolement de technétium 99m
EP4091178A4 (fr) * 2020-01-17 2024-09-04 BWXT Medical Ltd. Système et procédé pour la production d'isotopes du germanium-68
EP4588555A3 (fr) * 2020-01-17 2025-11-05 BWXT Medical, Inc. Système et procédé de production d'isotopes de germanium-68

Also Published As

Publication number Publication date
CN1264170C (zh) 2006-07-12
AU2002310305B2 (en) 2007-01-25
KR20040028770A (ko) 2004-04-03
JP4231779B2 (ja) 2009-03-04
WO2002099816A3 (fr) 2003-05-08
KR100858265B1 (ko) 2008-09-11
JP2004535288A (ja) 2004-11-25
CN1522448A (zh) 2004-08-18

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