EP1717819B1 - Système permettant la production automatique de radioisotopes - Google Patents

Système permettant la production automatique de radioisotopes Download PDF

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Publication number
EP1717819B1
EP1717819B1 EP05425262A EP05425262A EP1717819B1 EP 1717819 B1 EP1717819 B1 EP 1717819B1 EP 05425262 A EP05425262 A EP 05425262A EP 05425262 A EP05425262 A EP 05425262A EP 1717819 B1 EP1717819 B1 EP 1717819B1
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EP
European Patent Office
Prior art keywords
unit
target
target carrier
transfer means
irradiation
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EP05425262A
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German (de)
English (en)
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EP1717819A1 (fr
Inventor
Paolo Bedeschi
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Comecer SpA
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Comecer SpA
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Publication date
Priority to DK05425262.2T priority Critical patent/DK1717819T3/da
Application filed by Comecer SpA filed Critical Comecer SpA
Priority to ES05425262T priority patent/ES2369482T3/es
Priority to AT05425262T priority patent/ATE517418T1/de
Priority to EP05425262A priority patent/EP1717819B1/fr
Priority to US11/919,509 priority patent/US20100025251A1/en
Priority to CA2606643A priority patent/CA2606643C/fr
Priority to PCT/EP2006/061853 priority patent/WO2006114433A2/fr
Publication of EP1717819A1 publication Critical patent/EP1717819A1/fr
Application granted granted Critical
Publication of EP1717819B1 publication Critical patent/EP1717819B1/fr
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    • C—CHEMISTRY; METALLURGY
    • C25—ELECTROLYTIC OR ELECTROPHORETIC PROCESSES; APPARATUS THEREFOR
    • C25C—PROCESSES FOR THE ELECTROLYTIC PRODUCTION, RECOVERY OR REFINING OF METALS; APPARATUS THEREFOR
    • C25C1/00—Electrolytic production, recovery or refining of metals by electrolysis of solutions
    • C25C1/22—Electrolytic production, recovery or refining of metals by electrolysis of solutions of metals not provided for in groups C25C1/02 - C25C1/20
    • C—CHEMISTRY; METALLURGY
    • C25—ELECTROLYTIC OR ELECTROPHORETIC PROCESSES; APPARATUS THEREFOR
    • C25C—PROCESSES FOR THE ELECTROLYTIC PRODUCTION, RECOVERY OR REFINING OF METALS; APPARATUS THEREFOR
    • C25C7/00—Constructional parts, or assemblies thereof, of cells; Servicing or operating of cells
    • C25C7/007—Constructional parts, or assemblies thereof, of cells; Servicing or operating of cells of cells comprising at least a movable electrode
    • 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
    • H—ELECTRICITY
    • H05—ELECTRIC TECHNIQUES NOT OTHERWISE PROVIDED FOR
    • H05H—PLASMA TECHNIQUE; PRODUCTION OF ACCELERATED ELECTRICALLY-CHARGED PARTICLES OR OF NEUTRONS; PRODUCTION OR ACCELERATION OF NEUTRAL MOLECULAR OR ATOMIC BEAMS
    • H05H6/00—Targets for producing nuclear reactions

Definitions

  • the present invention relates to a system for automatically producing radioisotopes.
  • Radioisotopes have long been produced by cyclotron irradiation for medium- or low-energy (5-30 MeV) medical applications. Radioisotopes have many important industrial and scientific uses, the most important of which is as tracers : by reactions with appropriate nonradioactive precursors, radiodrugs are synthesized and, when administered in the human body, permit diagnosis and therapy monitoring by Positron Emission Tomography (PET), especially in the treatment of tumours. By measuring radiation, it is also possible to follow all the transformations of the element and/or related molecule in chemistry (reaction mechanism research), biology (metabolism genetics research), and, as stated, in medicine for diagnostic and therapeutic purposes.
  • PET Positron Emission Tomography
  • the only automated passage in known systems for producing radioisotopes is that between the irradiation station and the purifying station, where the desired radioisotope is separated not only from the target carrier material but also from the non-reacting target and any impurities ( W09707122 ).
  • the target carrier on which the starting metal isotope is deposited, is dissolved together with the target and subsequently removed from the manufactured radioisotope by means of a purification process.
  • the electrodeposition unit and the electrodissolution unit comprise the same electrolytic cell, and the first transfer means and second transfer means coincide.
  • first transfer means and second transfer means comprise a conduit connected to a pneumatic system and housing said target carrier in sliding manner.
  • Number 1 in Figure 1 indicates as a whole the system for automatically producing radioisotopes according to the present invention.
  • System 1 comprises an electrolysis unit 2 for both electrodeposition and electrodissolution; an irradiation unit 3 fixed directly to a cyclotron C; a purifying unit 4; transfer means 5 for transferring the target between electrolysis unit 2 and irradiation unit 3; transfer means 6 for transferring the dissolved target from electrolysis unit 2 to purifying unit 4; and a central control unit 7 for fully controlling operation of system 1.
  • System 1 comprises a target carrier 8 ( Figure 2 ) defined by a cylindrical wall 9 having a truncated-cone-shaped end portion 10, and by a partition wall 11 inside and perpendicular to cylindrical wall 9.
  • Partition wall 11 and cylindrical wall 9 define two separate cylindrical cavities 12 and 13. More specifically, cylindrical wall 9 thickens inwards at cavity 12; cylindrical wall 9 and partition wall 11 are made of aluminium or stainless steel; and cylindrical cavity 12 is lined with a coating 12a of platinum or niobium or iridium.
  • electrolysis unit 2 is supported on a supporting structure 14, which comprises a gripping head 15; four supporting members 16 on which to store four target carriers 8; and a terminal 17 for connecting a conduit 18, as described below.
  • Gripping head 15 is connected to a vacuum pump by a fitting 15a, and is moved vertically by a pneumatic cylinder and horizontally by a screw-nut screw system connected to a toothed belt.
  • Each supporting member 16 has a target carrier presence sensor.
  • Electrolysis unit 2 comprises an electrolytic cell 19; and a heater 20 housed, in use, inside cylindrical cavity 13 of target carrier 8.
  • electrolytic cell 19 comprises a delivery tube 21; a return tube 22 defining the dissolved target transfer means 6; a platinum electrode 23 with a corresponding platinum wire 24; a gold or platinum disk electrode 25; and four springs 26 wound about respective assembly screws, and which act on a disk body 27 for disconnecting target carrier 8.
  • Heater 20 comprises an electric resistor 28, and a temperature probe 29.
  • transfer means 5 for transferring target carrier 8 comprise a conduit 18 connected to a known pneumatic system (not shown for the sake of simplicity) by which the target carrier is pushed or drawn along conduit 18.
  • irradiation unit 3 comprises a grip pin 31 housed in use inside cylindrical cavity 13 of target carrier 8; a rotary actuator 32 connected to grip pin 31; a linear actuator 33 also connected to grip pin 31; and a pneumatic cylinder 34 connected to a terminal 35 of conduit 18.
  • inside grip pin 31 are formed a central cooling water feed conduit 36 connected to a fitting 37; an intermediate annular cooling water return conduit 38 connected to a fitting 39; and an outer annular conduit 40 connected to a vacuum pump by a fitting 41.
  • purification unit 4 comprises an ionic purification column 42, two pumps 43, a reactor 44, and a network of valves and vessels, and is electronically controlled to supply electrolytic cell 19 with the appropriate electrolytic solution containing the isotopes of the metals to be electrodeposited inside cavity 12 of target carrier 8, to supply electrolytic cell 19 with an HNO 3 solution for electrodissolving the irradiated target, to separate the radioisotope from the starting isotope and other radioactive impurities by ion chromatography, and to supply solvents for cleaning electrolytic cell 19, the transfer lines, and the components used to separate the radioisotope.
  • a target carrier 8 is picked up by gripping head 15 and placed on heater 20, so that heater 20 is housed inside cylindrical cavity 13 of target carrier 8; and electrolytic cell 19 is then lowered into the Figure 4 position, i.e. in which disk electrode 25 contacts an edge portion of coating 12a of cylindrical cavity 12 of target carrier 8.
  • an electrolytic solution from purifying unit 4 and in which the isotope of the metal to be deposited is dissolved, is fed in by delivery tube 21. As the solution flows in, the difference in potential is applied to the electrodes, and the isotope for irradiation is deposited.
  • electrolytic solution is removed, and electrolytic cell 19 and cylindrical cavity 12 are cleaned using deionized water and ethyl alcohol in succession, which are then removed by a stream of helium.
  • target carrier 8 is heated and maintained in a stream of gas to dry the deposited metal.
  • electrolytic cell 19 is raised, and gripping head 15 removes target carrier 8 and places it either on a supporting member 16, pending irradiation, or directly inside terminal 17, from which it is blown inside conduit 18 by a stream of compressed air.
  • Target carrier 8 is fed along conduit 18 to terminal 35 of irradiation unit 3, where the presence of carrier 8 is detected by a sensor.
  • target carrier 8 On reaching terminal 35, target carrier 8 is retained by grip pin 31 by virtue of the vacuum produced in outer annular conduit 40. Pneumatic cylinder 34 then lowers terminal 35 and conduit 18, and rotary actuator 32 and linear actuator 33 move grip pin 31 and target carrier 8 into the irradiation position. More specifically, carrier 8 is successively rotated 90° and translated to position cylindrical cavity 12 facing an irradiation opening 45 shown in Figure 5 . Once irradiated, target carrier 8 is replaced inside terminal 35 by linear actuator 33, rotary actuator 32, and pneumatic cylinder 34; at which point, the vacuum holding target carrier 8 on grip pin 31 is cut off, and the vacuum pump connected to conduit 18 is activated to return target carrier 8 to terminal 17.
  • the target carrier On reaching terminal 17, the target carrier is picked up by gripping head 15 and placed back on heater 20 as described previously; at which point, electrolytic cell 19 is lowered so that disk electrode 25 contacts the edge portion of coating 12a of cylindrical cavity 12 of target carrier 8. This time, however, unlike the electrodeposition operation described above, a portion of the coating of cylindrical cavity 12 is preferably left exposed to employ its catalyst properties for the electrodissolution reaction.
  • an acid solution from purifying unit 4 and comprising nitric or hydrochloric acid, is fed in by delivery tube 21, and target carrier 8 is appropriately heated by resistor 28.
  • electrodissolution is performed, by inverting one polarity of the electrodes with respect to electrodeposition, and the resulting solution is sent by a stream of inert gas to purifying unit 4.
  • the electrolysis unit is cleaned and dried using deionized water and ethyl alcohol, after which, gripping head 15 can pick up another target carrier 8 and commence another work cycle.
  • the acid solution from the electrodissolution operation and therefore containing the starting metal isotope and the radioisotope obtained by irradiation, is transferred to reactor 44 where the nitric acid is evaporated.
  • the isotope/radioisotope mixture is redissolved in a hydrochloric acid solution, radioactivity is measured, and the solution is transferred in a stream of helium to ionic purification column 42.
  • the starting metal isotope is recovered and used for further deposition.
  • a solution of 10 ml of ( 60 Ni, 61 Ni, 64 Ni) comprising nickel sulphate and boric acid is fed into a vessel in purifying unit 4.
  • target carrier 8 and electrolytic cell 19 are set up as shown in Figure 4
  • the nickel-containing acid solution is circulated, at a temperature of 25° to 50°C, inside cylindrical cavity 12 of target carrier 8 by a closed-circuit system supplied by one of pumps 43.
  • the voltage control is activated automatically and turns on the voltage and current supply pre-set to 3V and 20mA.
  • the electrodeposition operation lasts an average of 24h, after which, the system is arrested and, once the electrolytic solution circuit is emptied, electrolytic cell 19 and cavity 12 are cleaned using deionized water and ethyl alcohol in succession. Once the cleaning solvents are eliminated, target carrier 8 is heated to 60°C and maintained in a stream of gas for at least 15 minutes to dry the surface of the nickel deposit. The average yield of metal nickel on the bottom of cylindrical cavity 12 corresponds to 50 ⁇ 2% of the initially dissolved nickel. When the above operations are completed, target carrier 8 is transferred automatically along conduit 18 to the irradiation unit, and, after irradiation, is transferred automatically back to electrolysis unit 2.
  • electrolytic cell 19 while ensuring disk electrode 25 remains contacting the edge portion of coating 12a, is raised roughly 0.2 mm corresponding to an 88 cm 2 free-platinum surface formed on the lateral wall of cylindrical cavity 12.
  • the free-platinum surface acts as a catalyst in dissolving the nickel, which is done using a 5 ml solution of nitric acid 4M contained in a vessel in purifying unit 4.
  • the acid solution is circulated for about 10-20 minutes, at a flow rate of 0.5-2 ml/min, inside cylindrical cavity 12 of target carrier 8 heated to a temperature of 25 to 50°C; in which conditions, dissolution of the target is quantitative.
  • the acid solution containing the dissolved nickel and the manufactured radioisotope ( 60 Cu, 61 Cu, 64 Cu) is transferred automatically to purifying unit 4, where the manufactured radioisotope ( 60 Cu, 61 Cu, 64 Cu) is separated from the respective starting nickel isotope and any other radioactive and metal impurities.
  • a 10 ml solution of cadmium-110 comprising cadmium fluoborate and ammonium fluoborate is fed into a vessel in purifying unit 4 and to electrodeposition unit 2, where target carrier 8 and electrolytic cell 19 are set up as shown in Figure 4 .
  • the acid solution is circulated, at a temperature of 30°C and a flow rate of 0.5-2 ml/min, inside cylindrical cavity 12 by a closed-circuit system fed by one of pumps 43; and, in these conditions, 0.02 A current and 3V voltage are applied for about 4-6h to deposit at least 40mg of cadmium-110.
  • the system is cleaned with deionized water and ethyl alcohol, and, once the cleaning solvents are removed, target carrier 8 is heated to 60°C and maintained in a stream of gas for at least 15 minutes to dry the surface of the cadmium-110 deposit.
  • target carrier 8 is transferred automatically along conduit 18 to the irradiation unit, and, after irradiation, is transferred automatically back to electrolysis unit 2.
  • Electrodissolution is performed using a 4 ml solution of nitric acid 4M contained in a vessel in purifying unit 4.
  • the acid solution is circulated for about 2 minutes at a flow rate of 0.5-2 ml/min inside cylindrical cavity 12 of target carrier 8 maintained at ambient temperature; in which conditions, dissolution is quantitative.
  • the acid solution containing cadmium-110/indium-110 is transferred automatically to purifying unit 4, where the indium-110 is separated by ionic purification from the cadmium-110 and any other radioactive and metal impurities.
  • the system according to the present invention has the advantage of preparing radioisotopes automatically and so ensuring high output levels.
  • the system according to the present invention avoids dissolution of the target carrier, with obvious advantages at the purification stage.

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  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Physics & Mathematics (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Electrochemistry (AREA)
  • Organic Chemistry (AREA)
  • Metallurgy (AREA)
  • Materials Engineering (AREA)
  • Optics & Photonics (AREA)
  • General Engineering & Computer Science (AREA)
  • General Chemical & Material Sciences (AREA)
  • Plasma & Fusion (AREA)
  • Spectroscopy & Molecular Physics (AREA)
  • Electrolytic Production Of Non-Metals, Compounds, Apparatuses Therefor (AREA)
  • Electrolytic Production Of Metals (AREA)
  • Radiation-Therapy Devices (AREA)
  • Particle Accelerators (AREA)
  • Preparation Of Compounds By Using Micro-Organisms (AREA)
  • Medicines Containing Plant Substances (AREA)

Claims (13)

  1. Système (1) destiné à produire de manière automatique des radio-isotopes comprenant un porteur de cible (8), une unité d'électrodéposition (2) destinée à déposer par électrodéposition une cible dans ledit porteur de cible ; une unité d'irradiation (3) destinée à irradier ladite cible dans ledit porteur de cible (8); des premiers moyens de transfert (5, 18) destinés à transférer le porteur de cible à partir de l'unité d'électrodéposition (2) jusqu'à l'unité d'irradiation (3) ; une unité d'épuration (4) destinée à épurer le radio-isotope de la cible qui ne réagit pas et des impuretés ; et une unité de commande centrale (7) destinée à commander les unités opérationnelles et les moyens de transfert de façon à automatiser tout le procédé ; ledit système étant caractérisé par le fait qu'il comprend une unité d'électrodissolution (2) capable de dissoudre par électrodissolution ladite cible tout en évitant la dissolution du porteur de cible (8) ; des deuxième moyens de transfert (5, 18) destinés à transférer le porteur de cible à partir de l'unité d'irradiation (3) jusqu'à l'unité d'électrodissolution (3) ; des troisièmes moyens de transfert (6, 22) destinés à transférer la cible irradiée dissoute par électrodissolution à partir de l'unité d'électrodissolution (2) jusqu'à l'unité d'épuration (4).
  2. Système selon la revendication 1, caractérisé en ce que l'unité d'électrodéposition et l'unité d'électrodissolution comprennent la même cellule électrolytique (2) ; et en ce que lesdits premiers moyens de transfert (5, 18) et lesdits deuxièmes moyens de transfert (5, 18) coïncident.
  3. Système selon la revendication 2, caractérisé en ce que lesdits premiers moyens de transfert (5) et lesdits deuxièmes moyens de transfert (5) comprennent un conduit (18) qui est connecté à un système pneumatique et qui loge ledit porteur de cible (8) de manière coulissante.
  4. Système selon l'une quelconque des revendications précédentes, caractérisé en ce que ledit porteur de cible (8) comprend une paroi cylindrique (9), et une paroi de séparation (11) à l'intérieur et perpendiculaire à la paroi cylindrique (9) de façon à définir des première (12) et seconde (13) cavités cylindriques séparées l'une de l'autre ; ladite première cavité cylindrique (12) logeant la cible pour une irradiation.
  5. Système selon la revendication 4, caractérisé en ce que ladite paroi cylindrique (9) et ladite paroi de séparation (11) sont réalisées en aluminium ou en acier inoxydable ; et en ce que ladite première cavité cylindrique (12) est recouverte d'un revêtement (12a) réalisé en platine ou en niobium ou en iridium.
  6. Système selon la revendication 5, caractérisé en ce que ladite unité d'électrolyse comprend une cellule électrolytique (19) ; et un dispositif de chauffage (20) qui est logé dans ladite seconde cavité cylindrique (13) du porteur de cible (8).
  7. Système selon la revendication 6, caractérisé en ce que ladite cellule électrolytique (19) comprend une électrode réalisée en platine (23) ; et une électrode à disque (25) réalisée en or ou en platine et qui, en service, entre en contact avec une partie de bord du revêtement (12a) de la première cavité cylindrique (12) du porteur de cible (8).
  8. Système selon l'une quelconque des revendications précédentes, caractérisé en ce que ladite unité d'électrolyse (2) est fixée à une structure de support (14) qui comprend une tête de préhension pneumatique (15), et un certain nombre d'éléments de support (16) sur lesquels peuvent être stockés un nombre égal de porteurs de cible (8).
  9. Système selon l'une quelconque des revendications précédant, caractérisé en ce que ladite unité d'irradiation (3) comprend : une broche de préhension (31) ; un actionneur rotatif (32) connecté à la broche de préhension (31) ; et un actionneur linéaire (33) connecté également à la broche de préhension (31).
  10. Procédé destiné à produire des radio-isotopes comprenant une première étape consistant à déposer par électrodéposition un isotope de métal pour une irradiation à l'intérieur d'un porteur de cible (8) recouvert de platine ou d'iridium ou de niobium ; une deuxième étape consistant à irradier l'isotope de métal déposé ; et une quatrième étape consistant à épurer le radio-isotope de l'isotope de métal naissant et toutes autres impuretés métalliques et radioactives ; ledit procédé étant caractérisé par le fait qu'il comprend avant ladite quatrième étape, une troisième étape consistant à dissoudre par électrodissolution l'isotope de métal irradié et le radio-isotope formé tout en évitant la dissolution du porteur de cible (8).
  11. Procédé selon la revendication 10, caractérisé en ce que ladite troisième étape comprend la participation d'une partie de platine exempte de dépôts de surface.
  12. Procédé selon la revendication 11, caractérisé en ce que ladite partie de platine fait partie du revêtement dudit porteur de cible (8).
  13. Procédé selon l'une quelconque des revendications 10 à 12, caractérisé en ce que ledit isotope de métal est inclus dans le groupe qui comprend 60Ni 61Ni, 64Ni et 110Cd,
EP05425262A 2005-04-27 2005-04-27 Système permettant la production automatique de radioisotopes Active EP1717819B1 (fr)

Priority Applications (7)

Application Number Priority Date Filing Date Title
ES05425262T ES2369482T3 (es) 2005-04-27 2005-04-27 Sistema para producir radiosótopos automáticamente.
AT05425262T ATE517418T1 (de) 2005-04-27 2005-04-27 System zur automatischen gewinnung von radioisotopen
EP05425262A EP1717819B1 (fr) 2005-04-27 2005-04-27 Système permettant la production automatique de radioisotopes
DK05425262.2T DK1717819T3 (da) 2005-04-27 2005-04-27 System til automatisk at producere radioisotoper
US11/919,509 US20100025251A1 (en) 2005-04-27 2006-04-24 System for automatically producing radioisotopes
CA2606643A CA2606643C (fr) 2005-04-27 2006-04-26 Systeme de production automatique de radio-isotopes
PCT/EP2006/061853 WO2006114433A2 (fr) 2005-04-27 2006-04-26 Systeme de production automatique de radio-isotopes

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
EP05425262A EP1717819B1 (fr) 2005-04-27 2005-04-27 Système permettant la production automatique de radioisotopes

Publications (2)

Publication Number Publication Date
EP1717819A1 EP1717819A1 (fr) 2006-11-02
EP1717819B1 true EP1717819B1 (fr) 2011-07-20

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EP05425262A Active EP1717819B1 (fr) 2005-04-27 2005-04-27 Système permettant la production automatique de radioisotopes

Country Status (7)

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US (1) US20100025251A1 (fr)
EP (1) EP1717819B1 (fr)
AT (1) ATE517418T1 (fr)
CA (1) CA2606643C (fr)
DK (1) DK1717819T3 (fr)
ES (1) ES2369482T3 (fr)
WO (1) WO2006114433A2 (fr)

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US7781744B2 (en) * 2008-08-21 2010-08-24 Comecer S.P.A. Procedure for the preparation of radioisotopes
DE102009005893B3 (de) * 2009-01-23 2010-12-02 Forschungszentrum Jülich GmbH Verfahren zur Erzeugung von 11C sowie Targetkörper
JP5322071B2 (ja) * 2010-09-22 2013-10-23 独立行政法人放射線医学総合研究所 加速器による放射性核種の製造方法及び装置
US9991013B2 (en) 2015-06-30 2018-06-05 General Electric Company Production assemblies and removable target assemblies for isotope production
EP3608921B1 (fr) * 2018-08-06 2020-12-16 Ion Beam Applications S.A. Capsule pour un matériau cible et système d'irradiation dudit matériau cible
CA3109824A1 (fr) * 2018-08-27 2020-03-05 BWXT Isotope Technology Group, Inc. Systemes d'irradiation de cible pour la production de radio-isotopes
JPWO2020196793A1 (fr) * 2019-03-28 2020-10-01

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Publication number Priority date Publication date Assignee Title
CA935943A (en) * 1970-12-23 1973-10-23 Union Carbide Corporation Primary target for the production of fission products in a nuclear reactor and process for preparation
US5037602A (en) * 1989-03-14 1991-08-06 Science Applications International Corporation Radioisotope production facility for use with positron emission tomography
CA2055297C (fr) * 1990-11-13 1996-10-08 Iwao Kanno Appareillage et methode de production et d'injection automatique de h--o
AU7265096A (en) * 1995-08-09 1997-03-12 Newton Scientific, Inc. Production of 64cu and other radionuclides using charged-particle accelerator
US6153154A (en) * 1998-05-27 2000-11-28 Battelle Memorial Institute Method for sequential injection of liquid samples for radioisotope separations
US6157036A (en) * 1998-12-02 2000-12-05 Cedars-Sinai Medical Center System and method for automatically eluting and concentrating a radioisotope
US6221437B1 (en) * 1999-04-12 2001-04-24 Reynolds Tech Fabricators, Inc. Heated workpiece holder for wet plating bath
US20050006245A1 (en) * 2003-07-08 2005-01-13 Applied Materials, Inc. Multiple-step electrodeposition process for direct copper plating on barrier metals
EP1512774A1 (fr) * 2003-09-08 2005-03-09 Ion Beam Applications S.A. Procédé et dispositif pour la dissolution électrolytique d'éléments
ATE468589T1 (de) * 2004-09-28 2010-06-15 Soreq Nuclear Res Ct Israel At Verfahren und system zur herstellung von radioisotopen

Also Published As

Publication number Publication date
ES2369482T3 (es) 2011-12-01
CA2606643C (fr) 2013-09-03
DK1717819T3 (da) 2011-11-07
ATE517418T1 (de) 2011-08-15
CA2606643A1 (fr) 2006-11-02
US20100025251A1 (en) 2010-02-04
WO2006114433A2 (fr) 2006-11-02
EP1717819A1 (fr) 2006-11-02
WO2006114433A3 (fr) 2007-02-22

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