EP0141800B1 - Procédé et dispositif pour l'élution et le dosage d'un générateur d'isotopes - Google Patents

Procédé et dispositif pour l'élution et le dosage d'un générateur d'isotopes Download PDF

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Publication number
EP0141800B1
EP0141800B1 EP84890135A EP84890135A EP0141800B1 EP 0141800 B1 EP0141800 B1 EP 0141800B1 EP 84890135 A EP84890135 A EP 84890135A EP 84890135 A EP84890135 A EP 84890135A EP 0141800 B1 EP0141800 B1 EP 0141800B1
Authority
EP
European Patent Office
Prior art keywords
eluate
generator
radiation
filling
aspiration
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.)
Expired
Application number
EP84890135A
Other languages
German (de)
English (en)
Other versions
EP0141800A1 (fr
Inventor
Karl Gärtner
Gert Dr. Kriwetz
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.)
Boehringer Ingelheim RCV GmbH and Co KG
Original Assignee
Bender and Co GmbH
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 Bender and Co GmbH filed Critical Bender and Co GmbH
Publication of EP0141800A1 publication Critical patent/EP0141800A1/fr
Application granted granted Critical
Publication of EP0141800B1 publication Critical patent/EP0141800B1/fr
Expired legal-status Critical Current

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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

Definitions

  • the invention relates to a method and a device for eluting and metering a radioactive nucleide, in particular technetium, from a nucleus generator into a storage ampoule or the like, from which the eluate is removed for use.
  • the procedure is such that the generator is placed in a lead shield and connected to an eluate vessel containing a NaCl solution, by means of which the nucleus is eluted into an elution vessel which is also connected to the generator.
  • a sterile solution of 99 Tc m can be obtained as sodium pertechnetate.
  • the lead-coated elution vessel is then removed from the generator and the solution obtained is removed from the vessel for use by means of a syringe.
  • a device of the type described above is e.g. B. is shown in AT-B-335 578.
  • the invention therefore aims to provide a method and a device intended for carrying it out which enable a complete radiation-safe elution.
  • the invention relates to a method for eluting and dosing a radioactive nucleide, in particular technetium, from a nucleus generator into a storage ampoule or the like, from which the nucleus is removed for use, in which the generator arranged in a radiation-proof housing is firstly supplied to a supply for liquid nuclei solvent and on the other hand is connected to an eluate suction and metering device connected to a filling device;
  • This method is characterized in that the generator is then flushed under program control with a predeterminable amount of solvent and the eluate is transferred to an intermediate container of the suction device arranged in the radiation-proof housing, whereupon the radiation activity is measured and a predetermined amount of eluate is sent to the dosing device by means of the dosing device arranged in the radiation-proof housing Filling device provided in the radiation-proof housing is
  • This working method ensures that the operator is not exposed to radiation during and after the elution process, because all process steps take place fully automatically within a closed housing shielded from radiation.
  • the invention also relates to a device for carrying out the method according to the invention, with a housing shielded from radioactive radiation for accommodating a nucleus generator, a storage vessel for a liquid nucleus solvent, a device for connecting the storage vessel to the inlet of the generator, and a device for connecting the storage vessel and the output of the generator with a suction and metering device for the eluate, which in turn is connected to a filling station, in which the eluate or the like in a storage ampoule.
  • a housing shielded from radioactive radiation for accommodating a nucleus generator, a storage vessel for a liquid nucleus solvent, a device for connecting the storage vessel to the inlet of the generator, and a device for connecting the storage vessel and the output of the generator with a suction and metering device for the eluate, which in turn is connected to a filling station, in which the eluate or the like in a storage ampoule.
  • This device has the features that the storage vessel for liquid nuclei solvent, the connecting devices as well as the suction and metering device and the filling station are also arranged within the radiation-proof housing, and that the suction and metering device has a suction syringe, which has a controllable reusable valve with a storage container for the eluate is connectable to which a measuring device for measuring the radiation activity of the eluate is assigned, the suction and metering device and a rinsing and disinfecting station assigned to the filling station are connected to a waste container, and that a program control device for program control of the entire elution process is provided.
  • the filling station has a swivel arm mechanism which carries a filling needle connected to the suction and metering device and a ventilation needle and is pivotable between a filling position and a rinsing and disinfecting position and is slidably mounted for filling and rinsing.
  • a housing (not shown) for a nucleus generator 2, in particular technetium generator, is provided in a housing 1 shielded against radioactive radiation, the structure of which is known to the person skilled in the art.
  • a NaCl solution or a vessel 3 containing dilute hydrochloric acid is also inserted into the housing and connected to the inlet E of the generator 2 via a hose 4 ', in which a 3-way valve 5' is switched on.
  • An air filter 3 ' is also connected to line 4'.
  • the vessel 3 containing the NaCl solution is also connected to the via a hose line 4 "and a 3-way valve 5" switched into this line Output of generator 2 in connection.
  • a further hose line 4 ′ ′′ extends from the valve 5 ′′ to a suction and metering device, generally designated 6.
  • This device can be connected via a 4-way valve 7 to the valve 5 ′′, to an eluate reservoir 8 and to an eluate filling station, generally designated 9.
  • a measuring device 10 for determining the radiation activity of the eluate is assigned to the eluate reservoir 8.
  • the storage container 8 can be connected on the one hand to the filling station 9 via the valve 7, and on the other hand via a ventilation line 8 'and a 3-way valve 12 connected to an air filter 11 with a waste container 13.
  • a swivel arm mechanism 14 for an eluate vessel 15, a piercing ampoule in the example shown.
  • the swivel arm 14 can be pivoted in the horizontal direction between a filling position F in the filling station 9 and a rinsing and disinfecting position S in a rinsing and disinfecting station 17 and can be displaced in the vertical direction.
  • the swivel arm 14 is provided at its lower end with a carrier 14 'for two needles 16', 16 ". One longer needle 16 'is connected to the valve 7, while the other shorter needle 16" is connected via a hose line 8 " is connected to the waste container 13.
  • the station 17 for rinsing and disinfecting the needles 16 ', 16 is connected via a hose line 17' and a pump 19 to a storage vessel 18 for a disinfectant and rinsing liquid, and is connected via a further line 17" in connection with the waste container 13.
  • a lock 20 is provided in the wall of the housing 1 for inserting and removing the eluate vessel 15.
  • the device is also provided with a program control device, not shown, for program control of the entire workflow.
  • program control devices are known to the person skilled in the art and therefore do not need to be explained in more detail.
  • the device explained above works as follows: after inserting the nucleus generator 2 and the NaCl vessel 3 into the housing 1 and connecting the hose lines 4 ′, 4 ′′ to the generator 2, for example by closing the housing 1
  • the valve 5 ' is brought into a blocking position and the valve 5 "is switched so that the vessel 3 is connected to the 4-way valve 7 .
  • the valve 7 is in turn switched so that it is connected to a syringe 6 'arranged in the device 6 so that it can draw in the NaCl solution.
  • the valve 12 is switched so that the reservoir 8 is vented or can be flushed to the waste container 13.
  • the valve 7 is then switched to release the connection between the syringe 6 'and the storage container 8, whereupon the syringe 6' presses the sucked-in NaCl solution into the storage container 8 until it is filled.
  • the valve 12 is then switched so that the reservoir 8 is only connected to the air filter 11, whereupon the syringe 6 'sucks the liquid out of the reservoir 8 again.
  • the valve 7 then connects the syringe 6 'to the needle 16' pivoted into the rinsing position 8 and the syringe 6 'rinses the previously sucked-in contents of the storage container 8 via the needle 16' and the line 17 "into the waste container 13.
  • the program control is such that the valve 5 'first connects the NaCI vessel 3 to the input E of the generator 2 and the valve 5 "the output A of the generator to the valve 7, which establishes the connection with the syringe 6'.
  • the valve 7 then switches to the connection between the syringe 6' and the rinsing station 17, in which the Swivel arm 14 with the needles 16 ', 16 "is in the starting position, and the syringe 6' empties via the needle 16 'and the line 17" into the waste container 13.
  • the valve 7 then switches back to connection between the output A of the Generator 2 and the syringe 6 ', so that the predetermined amount of solution can be sucked in, minus the amount that is in the lines between the valve 5', the generator 2 and the valve 5 "to the entrance of the syringe 6 ' indet.
  • the generator 2 is drained by repeated suction of air by means of the syringe 6 'via the valve 5', the generator 2, the valve 5 ", the valve 7 and by blowing out the air via the valve 7 and the flushing station 17.
  • the NaCl solution is sucked in by the syringe 6 'via the valves 5 "and 7 until the inlet of the syringe 6' is reached, whereupon the syringe 6 'is emptied into the rinsing station 17.
  • the desired amount is now removed from the storage container 8 aspirated, if necessary, a dilution amount of NaCI and then pressed up to the filling needles 16, 16 'in order to empty the line 7'.
  • the desired eluate bottle 15 has been transported into the filling station 9 via a transport device, not shown, and the bottle cap has been disinfected.
  • the needles 16 ′, 16 ′′ which have been conveyed into the filling station are moved downwards against the bottle 15 in this station 9 to such an extent that the first needle 16 ′ pierces the rubber closure cap 15 ′ of the bottle 15 and the filling of the eluate by means of the syringe 6.
  • the needles 16', 16 "are moved further downward after a short filling time, so that the second needle 16" pierces the bottle cap and the air - or excess nitrogen discharges via a line 12 'into the waste container 13.
  • the needles 16', 16 are pulled out of the closure and pivoted by means of the arm 14 into the rinsing and disinfecting station 17 in order to disinfect them to become.
  • the filled vial 15 is conveyed into a rotatable storage station (not shown) arranged in the housing 1, cooled, heated as required or stored at room temperature until it is used.
  • the bottle 15 which is provided with a lead shield, is conveyed into the lock 20, in which an opening is provided, through which the required amount can be withdrawn from the vial 15 with an injection needle.
  • the device shown can be modified in various ways within the scope of the general inventive concept.
  • the suction syringe 6 'of the suction and metering device can be replaced by a vacuum pump, the latter, however, having to be arranged at a different location than the one shown.
  • the swivel arm mechanism could also be replaced by another mechanical device. It is further understood that the entire elution process takes place under sterile conditions.

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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)
  • Sampling And Sample Adjustment (AREA)
  • Measurement Of Radiation (AREA)
  • Medicines Containing Antibodies Or Antigens For Use As Internal Diagnostic Agents (AREA)
  • Nuclear Medicine (AREA)
  • Infusion, Injection, And Reservoir Apparatuses (AREA)

Claims (4)

1. Procédé d'élution et de dosage d'un nucléide radio-actif, en particulier du technétium, hors d'un générateur de nucléides dans une ampoule de réserve ou analogue, de laquelle le nucléide est prélevé en vue de l'utilisation, suivant lequel le générateur agencé dans un boîtier à l'épreuve du rayonnement est raccordé, d'une part à une réserve pour du solvant liquide du nucléide et d'autre part, à un appareil d'aspiration d'éluat et de dosage se trouvant en communication avec un appareil de remplissage, caractérisé en ce que le générateur est ensuite rincé par commande programmée à l'aide d'une quantité de solvant déterminable au préalable et l'éluat est transféré dans un récipient intermédiaire de l'appareil d'aspiration agencé dans le boîtier à l'épreuve du rayonnement, après quoi l'activité du rayonnement est mesurée et une quantité déterminée au préalable d'éluat est débitée, à l'aide de l'appareil de dosage agencé dans le boîtier à l'épreuve du rayonnement, dans l'appareil de remplissage agencé aussi dans le boîtier à l'épreuve du rayonnement et dans lequel cette quantité est introduite dans une ampoule à percer qui est déplacée avec son obturateur au ras d'un orifice du boîtier à l'épreuve du rayonnement par lequel la quantité d'éluat en question est prélevée de l'ampoule à percer depuis l'extérieur du boîtier.
2. Installation pour la conduite du procédé suivant la revendication 1, comprenant un boîtier (1) protégé contre le rayonnement radio-actif pour recevoir un générateur de nucléides (2), un réservoir (3) pour un solvant liquide du nucléide, un appareil (4', 5') pour la mise en communication du réservoir avec l'entrée du générateur, un appareil (4", 5") pour la mise en communication du réservoir et de la sortie du générateur avec un appareil d'aspiration et de dosage (6) pour l'éluat qui se trouve en communication à son tour avec un poste de remplissage (9) dans lequel l'éluat est introduit dans une ampoule de reserve ou analogue, caractérisée en ce que le réservoir (3) pour le solvant liquide du nucléide, les appareils de mise en communication (4', 4"; 5', 5"), de même que l'appareil d'aspiration et de dosage (6) et le poste de remplissage (9) sont également agencés à l'intérieur du boîtier (1) à l'épreuve du rayonnement, l'appareil d'aspiration et de dosage (6) comporte une seringue d'aspiration (6') qui peut être mise en communication, par l'intermédiaire d'un robinet à plusieurs voies réglable (7), avec un réservoir (8) pour l'éluat, auquel est adjoint un appareil de mesure (10) pour la mesure de l'activité du rayonnement de l'éluat, l'appareil d'aspiration et de dosage (6) et un poste de rinçage et de désinfection (17) adjoint au poste de remplissage (9) se trouvent en communication avec un récipient de déchets (13) et un appareil de commande programmée est prévu pour la commande programmée de l'ensemble du processus d'élution.
3. Installation suivant la revendication 2, caractérisée en ce que le poste de remplissage (9) comporte un mécanisme à bras oscillant (14) qui porte une aiguille de remplissage (16') se trouvant en communication avec l'appareil d'aspiration et de dosage (6) et une aiguille d'aération (16") et qui est agencé de façon à pouvoir permuter d'une position de remplissage à une position de rinçage et de désinfection ainsi que du remplissage au rinçage.
4. Installation suivant la revendication 2 ou 3, caractérisée en ce que l'appareil (4', 5') pour la mise en communication du réservoir (3) pour le solvant liquide du nucléide avec l'entrée du générateur (2) comporte un robinet à plusieurs voies réglable (5'), par l'intermédiaire duquel le générateur (2) peut être mis en communication avec l'atmosphère.
EP84890135A 1983-08-17 1984-07-19 Procédé et dispositif pour l'élution et le dosage d'un générateur d'isotopes Expired EP0141800B1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
AT2948/83 1983-08-17
AT0294883A AT379253B (de) 1983-08-17 1983-08-17 Verfahren und vorrichtung zum eluieren und dosieren eines radioaktiven nukleids

Publications (2)

Publication Number Publication Date
EP0141800A1 EP0141800A1 (fr) 1985-05-15
EP0141800B1 true EP0141800B1 (fr) 1987-10-14

Family

ID=3542885

Family Applications (1)

Application Number Title Priority Date Filing Date
EP84890135A Expired EP0141800B1 (fr) 1983-08-17 1984-07-19 Procédé et dispositif pour l'élution et le dosage d'un générateur d'isotopes

Country Status (9)

Country Link
US (1) US4625118A (fr)
EP (1) EP0141800B1 (fr)
JP (1) JPH0750200B2 (fr)
AT (1) AT379253B (fr)
CA (1) CA1220881A (fr)
DE (1) DE3466824D1 (fr)
DK (1) DK170104B1 (fr)
ES (1) ES8605108A1 (fr)
NO (1) NO162174C (fr)

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US4853546A (en) * 1986-09-16 1989-08-01 Ube Industries, Ltd. Automatic radioisotope filling apparatus
AT391763B (de) * 1988-09-13 1990-11-26 Bender & Co Gmbh Einrichtung zum messen der aktivitaet und des volumens radioaktiver fluessigkeiten
US5039863A (en) * 1988-11-15 1991-08-13 Ube Industries, Ltd. Automatic radioisotope filling apparatus
ATE154722T1 (de) * 1991-05-01 1997-07-15 Mallinckrodt Medical Inc Verfahren zur förderung von flüssigen materialien und vorrichtung zur automatischen eluierung eines radionuklidgenerators
CN1035736C (zh) * 1992-10-14 1997-08-27 中国核动力研究设计院 凝胶型锝-99m发生器自动分装装置
GB0305848D0 (en) * 2003-03-14 2003-04-16 Imaging Res Solutions Ltd Radiopharmaceutical generation system
WO2005057589A2 (fr) * 2003-11-05 2005-06-23 Board Of Regents, The University Of Texas System Dispositif de synthese de marqueurs radioactifs automatise multifonction
WO2005083393A1 (fr) * 2004-01-27 2005-09-09 Arcana International, Inc. Systeme de commande, de verification et d'enregistrement des performances des operations effectuees par un generateur de radio-isotopes
US7163031B2 (en) * 2004-06-15 2007-01-16 Mallinckrodt Inc. Automated dispensing system and associated method of use
DE102005031920B4 (de) * 2005-07-07 2007-12-20 Isotopen Technologien München AG Vorrichtung und Verfahren zur Herstellung einer geringen Menge einer radioaktiven Substanzverbindung
CA2618604A1 (fr) * 2005-08-09 2007-03-05 Mallinckrodt Inc. Systeme de generation de radio-isotopes partiellement aptes a l'elution
ITBO20060128A1 (it) * 2006-02-21 2007-08-22 Tema Sinergie S R L Macchina dosatrice di liquido radioattivo.
US7862534B2 (en) * 2008-06-11 2011-01-04 Bracco Diagnostics Inc. Infusion circuit subassemblies
AU2009257432B2 (en) 2008-06-11 2014-11-13 Bracco Diagnostics Inc. Infusion systems including computer-facilitated maintenance and/or operation
US9597053B2 (en) * 2008-06-11 2017-03-21 Bracco Diagnostics Inc. Infusion systems including computer-facilitated maintenance and/or operation and methods of use
US8708352B2 (en) * 2008-06-11 2014-04-29 Bracco Diagnostics Inc. Cabinet structure configurations for infusion systems
US8317674B2 (en) 2008-06-11 2012-11-27 Bracco Diagnostics Inc. Shielding assemblies for infusion systems
US8216181B2 (en) * 2008-11-19 2012-07-10 Bracco Diagnostics, Inc. Apparatus and methods for support of a membrane filter in a medical infusion system
CN102249352B (zh) * 2011-05-23 2013-03-20 中国工程物理研究院核物理与化学研究所 医用高锝酸盐自动生产装置
AU2015229189B2 (en) 2014-03-13 2020-04-09 Bracco Diagnostics Inc. Real time nuclear isotope detection
US11752254B2 (en) 2016-09-20 2023-09-12 Bracco Diagnostics Inc. Radioisotope delivery system with multiple detectors to detect gamma and beta emissions
EP3776599B1 (fr) 2018-03-28 2023-09-13 Bracco Diagnostics Inc. Détection précoce de la durée de vie d'un générateur de radio-isotopes
RU2754815C1 (ru) * 2020-09-29 2021-09-07 федеральное государственное бюджетное образовательное учреждение высшего образования "Ульяновский государственный университет" Способ дозирования и фасовки фармацевтических субстанций и устройство для его реализации

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DE6944639U (de) * 1968-11-25 1970-06-04 Squibb & Sons Inc Geraet zum abgeben von radioaktivem material
FR2053665A5 (en) * 1969-07-11 1971-04-16 Commissariat Energie Atomique Handling short lived radioactive samples automatically
US3710118A (en) * 1970-05-25 1973-01-09 Mallinckrodt Chemical Works Radioisotope generator
US3774035A (en) * 1971-07-12 1973-11-20 New England Nuclear Corp Method and system for generating and collecting a radionuclide eluate
JPS4928879A (fr) * 1972-07-14 1974-03-14
DE2236565C3 (de) * 1972-07-26 1979-05-03 Hoechst Ag, 6000 Frankfurt Vorrichtung zum Herstellen von sterilen, injizierbaren Eluaten durch Eluieren von Nuklidgeneratoren
US3997784A (en) * 1975-06-16 1976-12-14 Union Carbide Corp Automatic apparatus for dispensing radiodiagnostic agents and method therefor
JPS5715899A (en) * 1980-07-02 1982-01-27 Ebara Infilco Co Ltd Treatment of organic waste water
US4472299A (en) * 1981-04-24 1984-09-18 Amersham International Plc Generator for radionuclide and process of use thereof

Also Published As

Publication number Publication date
DE3466824D1 (en) 1987-11-19
AT379253B (de) 1985-12-10
DK370684A (da) 1985-02-18
DK370684D0 (da) 1984-07-30
NO162174C (no) 1989-11-15
ES535121A0 (es) 1986-03-16
ES8605108A1 (es) 1986-03-16
EP0141800A1 (fr) 1985-05-15
US4625118A (en) 1986-11-25
ATA294883A (de) 1985-04-15
DK170104B1 (da) 1995-05-22
JPS6070400A (ja) 1985-04-22
NO843284L (no) 1985-02-18
NO162174B (no) 1989-08-07
CA1220881A (fr) 1987-04-21
JPH0750200B2 (ja) 1995-05-31

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