US3898044A - Eluting device for nuclide generators - Google Patents

Eluting device for nuclide generators Download PDF

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Publication number
US3898044A
US3898044A US382134A US38213473A US3898044A US 3898044 A US3898044 A US 3898044A US 382134 A US382134 A US 382134A US 38213473 A US38213473 A US 38213473A US 3898044 A US3898044 A US 3898044A
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United States
Prior art keywords
container
eluate
generator
nuclide
pump
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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 - Lifetime
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US382134A
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English (en)
Inventor
Helmut Strecker
Karl-Heinz Tetzlaff
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Hoechst AG
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Hoechst AG
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Publication date
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    • 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
    • G21G1/0005—Isotope delivery systems
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F7/00—Shielded cells or rooms
    • G21F7/06—Structural combination with remotely-controlled apparatus, e.g. with manipulators
    • G21F7/068—Remotely manipulating devices for fluids

Definitions

  • PI'iHKU [:It'umineF-A. Louis Monacell Assistant EtmuiuerS. J. Emery [30] J l iz gl g Priority Dam 65 Attorney, Agent, or Firm-Curtis, Morris & Sufford u y ermuny -2 A CT [52] [1.5. C1 1. 23/252 R; 23/267 R; 23/2726 R; FSTRA 252/30] R Device for elutmg nuchde generators compnsmg a nu [51] Int. Cl H Bold 11/02: (Elf 5/00. G21 ⁇ , 5/02 clide generator conveying means.
  • Nuclide generators serve to apply radio-nuclides of short life time in medicine and technics.
  • a radio-active mother nuclide of longer life time produces a short lived daughter nuclide which can repeatedly be cluated by a separating column.
  • a closed sterile system composed of eluting agent, column, eluate container and transfer system eluates are obtained which can be injected or are suitable for making injectable prepara tions.
  • the eluate container is evacuated so that the eluting agent is sucked through the column.
  • the flowing rate of the eluting agent is not constant and fractional elution is difficult.
  • the invention provides a device for eluting nuclide generators wherein the container for the eluting agent, the container for the eluate and the conveying means are connected with the nuclide generator by conduits, the conveying means are positioned between the container for the eluting agent and the container for the eluate, and the conveying means com prise a control device allowing of conveying freely cligible amounts of eluate into the eluate container.
  • the conveying means are arranged between the container for the eluting agent and the nuclide generator.
  • the conveying means can be installed between the nuclide generator and the eluate container.
  • nuclide generator, container for eluting agent, conveying means and eluate container are preferably connected with one another by means of plug connections.
  • the eluate container should be placed in a transparent casing protecting against radiation.
  • the tube pump has the property to convey, independent of the flow resistance of the column, a constant mass flow.
  • the constant mass flow produces a uniform activity distribution.
  • the high pump pressure permits to use finegrained and hence very active ion exchangers and other active substances for the column. With the high permissible pressure loss in the column greater ratios of col' umn length to column cross section can be used. Finally, the high pump pressure allows of installing filters.
  • the device of the invention offers a great security as regards the course of operation and protection against radiation.
  • FIG. I is a simplified representation of the mode of operation of the device.
  • FIG. 2 is a sectional view of the device according to the invention.
  • FIG. 3 is a top view of the device according to the invention.
  • FIG. 4 is a fragmentary sectional view of a variant of the device as shown in FIG. 2.
  • FIG. 5 illustrates a mode of execution of the shut off valves.
  • FIG. 6 represents the tube pump with lubricating means.
  • FIG. 7 is a fragmentary sectional view of the generator connection.
  • FIG. 8 is a fragmentary sectional view of a special embodiment of the supply section of the device shown in FIG. 2.
  • a container I for the eluting agent preferably a bag of plastic material provided with an impervious junction 2 which can be pierced by a hollow needle is connected with a conduit 4 by an injection needle 3.
  • Conduit 4 has a fix point 5 to which a conduit 8 is connected leading to the conveying device 9.
  • conveying devices rotary pumps with small dead volume and hermetically sealed with respect to the outside can be used, for example tube pumps. diaphragm pumps, or bellows pumps, a statorless tube pump being especially suitable.
  • the preferably three cornered pump impeller carries an absorbent layer 10, for example a sponge, tissue, or hide, for a lubricating liquid, for for example glycerol, which continuously lubricates the pump hose 8 preferably made of silicone rubber or a similar elastic material.
  • an absorbent layer 10 for example a sponge, tissue, or hide
  • a lubricating liquid for for example glycerol
  • nuclide generator From the conveying device the current of conveyed fluid is passed over a second fix point 11, which provides for the right tension of the tube together with fix point 5, and through conduit 12 it arrives at the entrance of nuclide generator [3.
  • the nuclide generator is positioned in a protecting casing 14.
  • Conduit 12 is connected to the nuclide generator by an injection needle which may be curved.
  • the junctions of nuclide generator 13 are provided with piercable stoppers made of an elastic material.
  • a hose [6 is pulled over which is pushed back when the needle is prieked through the stopper.
  • the outlet of nuclide generator 13 has the same construction as the inlet.
  • the protecting casing 14 need not be opened.
  • conduit l7 leads to eluate container 2] via injection needle as eluate container an injection flask with evacuation tube 22 may be used.
  • Conduit 4 may additionally be provided with a branching 6, formed, for example. of a valve stopper 5a, simultaneously serving as fix point 5, with two connections.
  • Conduit 6 is connected with conduit 1711 via a second valve stopper 7 and conduit 17a is connected with eluate container 21 by way of valve stopper 7, injection needle 18, conduit 19 and injection needle 20.
  • As eluate container there may also be used an injection syringe 26 directly linked up with injection needle 18 via valve stopper 7. With pulled out injection needle [8 the eluate is recycled to the entrance of the nuclide generator through conduit 6 by means of conveying device 9.
  • valve stopper 5a With the aid of valve stopper 5a a nuclide generator linked to the system of conduits can be charged with the mother nuclide or. if the conveying device fails, it can be eluated by an injection syringe.
  • valve stopper 7 two valves 24 and 25 can be used, for example tube clips.
  • the conveying device 9 is driven by electric means.
  • the power supply for example battery 27, can be installed in the device.
  • the revolution of the pump impeller or the stroke frequency of the pump is firmly connected by way of speed reducers with a preselection device 28 switching off the conveying device after the de sired amount has been conveyed.
  • the speed reduction can be effected. for example. by a gear connected with a selecting disk with a plate cam on the same shaft which actuates a switch.
  • the selecting disk can be set to the desired amount by a safety clutch or a friction gear.
  • the conveying device is switched on by means of a push-button switch.
  • the dosing head 30 which is set in an unchangeablc position on top of the potshaped supply section 31. Dosing head and conveying device are then connected by a suitable coupling. for example toothed wheels. drivers and magnets.
  • a suitable coupling for example toothed wheels. drivers and magnets.
  • supply section 31 containing parts I to 11 and in part conduits l2 and 17a readily accessible from above and also laterally at the conveying device.
  • Supply section 3] is provided with an additional disk-shaped radiation shield 32. The lateral and lower additional protection against radiation is ensured by a pot-shaped container 33, on which the entire device rests.
  • a transparent con tainer 34 for example of lead glass, or a container with double walls the clearing of which is filled with a solution of elements of high atomic number.
  • Container 34 is closed by a detachable cover 35 having at least one small boring for injection needles.
  • the supply section 31 is firmly connected with the protecting casing 36 containing the nuclide generator. All parts i to [7a are mounted in this combination preferably ready for instant use. ln this case the nuclide generator and the container for the eluting agent are provided with stationary connections.
  • the container 36 is attached to a disk 37 in tight and solid manner. By means of a tension ring 38 and a sealing 39 a hood 40 is clamped on the said disk. After having inserted the tight transportable unit into container 33, removed hood 40 and mounted dosing head 30 on top it is ready for use.
  • EXAMPLE 1 In a nuclide generator consisting of a column filled with 6 grams ofaluminium oxide and having 1 milliliter of dead space at each end closed by a rubber stopper radioactive Tc is to be separated from Mo emanating 50 mCi. With 11 ml of physiological sodium chlo ride solution almost the entire amount of 45 mCi Tc capable of being washed out can be eluated. To obtain a higher activity concentration, for example. 42.3 mCi Tc can be washed out with 8.3 milliliters. corresponding to an activity concentration of 10.2 mCi/ml. To this effect the device as shown in FIGS. 2, 3 and 5 is used.
  • 8.3 Milliliters are set on selecting disk 28 and push-button switch 29 is actuated, whereupon eluate is pumped by tube pump 9 into the shielded eluate container 21. After conveyance of 8.3 milliliters the pump is automatically switched off. The elution is terminated. When needed the eluate can be taken from eluate container 21 by an injection syringe.
  • EXAMPLE 2 Out of a nuclide generator as described in Example I, 6 injection syringes of high activity and ready for immediate use are to be filled within a period of 5 hours at equal intervals.
  • a high amount by vol time is set. for example 23 milliliters.
  • push-button switch 29 is actuated whereby a mixing process is started since the eluate flows back through conduit 6 to the entrance ofthe nuclide generator.
  • the uniform activity concentration would permit to take with several injection syringes up to about of the activity capable of being washed out.
  • injection syringe 26 is pushed through valve stopper 7 and push-button switch 29 is actuated. in this manner 6 times 6.2 mCi are obtained.
  • a mixing is performed prior to each filling of the syringe a mixing is performed prior to each filling of the syringe a mixing is performed prior to each filling of the syringe a mixing is performed.
  • Example 2 If this example were carried out in the manner described in Example 1, 6 times 4.25 mCi could be taken. In both cases the activity concentration is approximately equal. With the first extraction the activity concentration according to Example 2 is by 7% higher and with the last extraction by 7% lower than in Example 1.
  • a device for cluting nuclide generators comprising a radiation shield container having an open top. a nuclide generator positioned in said container; a housing removably mounted on said container adjacent said open top and including a container for an eluting agent, a container for receiving eluate from said generator, a plurality of conduits connecting said eluting agent container through said open top to said generator and said generator to said eluate container.
  • said pump means including selectively operable control means for limiting operation of said pump to pump only a predetermined amount of eluate into the eluate container said pump means being installed in said housing between the container for the eluting agent and the container for said nuclide generator and being operatively associated with the conduit therebetween'. and said conduit connecting the nuclide generator with the eluate container including a branching conduit connccted to the conduit connecting the nuclide generator with the container for eluting agent. thereby to provide a recirculating path between said housing and said generator.
  • said pump means comprises an electrically driven pump which is hermetically sealed in said housing.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • General Chemical & Material Sciences (AREA)
  • Infusion, Injection, And Reservoir Apparatuses (AREA)
  • External Artificial Organs (AREA)
  • Sampling And Sample Adjustment (AREA)
  • Medical Preparation Storing Or Oral Administration Devices (AREA)
  • Medicines Containing Antibodies Or Antigens For Use As Internal Diagnostic Agents (AREA)
US382134A 1972-07-26 1973-07-24 Eluting device for nuclide generators Expired - Lifetime US3898044A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE2236565A DE2236565C3 (de) 1972-07-26 1972-07-26 Vorrichtung zum Herstellen von sterilen, injizierbaren Eluaten durch Eluieren von Nuklidgeneratoren

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US3898044A true US3898044A (en) 1975-08-05

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US382134A Expired - Lifetime US3898044A (en) 1972-07-26 1973-07-24 Eluting device for nuclide generators

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US (1) US3898044A (US20110158925A1-20110630-C00042.png)
JP (1) JPS4957298A (US20110158925A1-20110630-C00042.png)
AT (1) AT335578B (US20110158925A1-20110630-C00042.png)
AU (1) AU469264B2 (US20110158925A1-20110630-C00042.png)
BE (1) BE802839A (US20110158925A1-20110630-C00042.png)
BR (1) BR7305651D0 (US20110158925A1-20110630-C00042.png)
CH (1) CH559959A5 (US20110158925A1-20110630-C00042.png)
DD (1) DD105392A5 (US20110158925A1-20110630-C00042.png)
DE (1) DE2236565C3 (US20110158925A1-20110630-C00042.png)
ES (2) ES417088A1 (US20110158925A1-20110630-C00042.png)
FR (1) FR2194021B1 (US20110158925A1-20110630-C00042.png)
GB (1) GB1428669A (US20110158925A1-20110630-C00042.png)
IL (1) IL42812A (US20110158925A1-20110630-C00042.png)
IT (1) IT992668B (US20110158925A1-20110630-C00042.png)
NL (1) NL7310153A (US20110158925A1-20110630-C00042.png)
SU (1) SU479307A3 (US20110158925A1-20110630-C00042.png)
ZA (1) ZA734837B (US20110158925A1-20110630-C00042.png)

Cited By (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4414145A (en) * 1979-04-17 1983-11-08 Byk-Millinkcrodt Cil B.V. Preparation and use of a 195M-AU-containing liquid
US4472299A (en) * 1981-04-24 1984-09-18 Amersham International Plc Generator for radionuclide and process of use thereof
US4643891A (en) * 1979-04-17 1987-02-17 Mallinckrodt Diagnostica (Holland) B.V. Preparation and use of a 195m Au-containing liquid
US4919900A (en) * 1987-01-21 1990-04-24 Aerospatiale Societe Nationale Industrielle System for crystal growth, particularly for space vessel
US5326532A (en) * 1993-02-25 1994-07-05 E. I. Du Pont De Nemours And Company Apparatus for chemically processing toxic materials
US5580541A (en) * 1991-05-01 1996-12-03 Mallinkrodt Medical, Inc. Method of conveying liquid materials and device for the automated elution of a radionuclidic generator
GB2382453A (en) * 2002-04-11 2003-05-28 Amersham Plc Radioisotope generator and method of construction thereof
US20050278066A1 (en) * 2004-06-15 2005-12-15 Kevin Graves Automated dispensing system and associated method of use
US20080191148A1 (en) * 2005-08-09 2008-08-14 Gibson Chad M Radioisotope Generation System Having Partial Elution Capability
US20080224065A1 (en) * 2005-08-29 2008-09-18 Pollard Jr Ralph E System and Method for Eluting Radioisotope to a Container Disposed Outside of a Radioisotope Generator Assembly
EP3101659A1 (en) * 2006-10-06 2016-12-07 Mallinckrodt Nuclear Medicine LLC Self-aligning radioisotope elution system

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5712684Y2 (US20110158925A1-20110630-C00042.png) * 1976-09-01 1982-03-13
DE2800496A1 (de) * 1978-01-05 1979-07-19 Heyden Chem Fab Radionuklidgenerator
AT379253B (de) * 1983-08-17 1985-12-10 Bender & Co Gmbh Verfahren und vorrichtung zum eluieren und dosieren eines radioaktiven nukleids
DE8621529U1 (de) * 1986-08-11 1986-10-30 Von Heyden GmbH, 8000 München Dosiervorrichtung für Radionuklidgeneratoren
WO1997045841A1 (fr) * 1996-05-29 1997-12-04 Gosudarstvenny Nauchny Tsentr Fiziko-Energetichesky Institut Dispositif de production de radionucleides steriles
GB2386743B (en) * 2002-04-11 2004-02-11 Amersham Plc Radioisotope generator
ITPD20100186A1 (it) * 2010-06-11 2011-12-12 Attilio Cecchin Apparecchio per eluizione e procedimento di eluizione

Citations (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2123212A (en) * 1933-09-28 1938-07-12 Scholler Heinrich Process of extraction
US2427042A (en) * 1946-04-03 1947-09-09 Gulf Research Development Co Method and apparatus for separating mixtures
US2968721A (en) * 1954-09-27 1961-01-17 Tracerlab Inc Methods of flow rate measurement
US3156532A (en) * 1961-06-30 1964-11-10 Robert F Doering Yttrium-90 generator
US3510271A (en) * 1963-04-11 1970-05-05 Pharmacia Fine Chem Inc Chromatographic separation employing a gel bed
US3535085A (en) * 1967-08-07 1970-10-20 Mallinckrodt Chemical Works Closed system generation and containerization of radioisotopes
US3561932A (en) * 1967-01-26 1971-02-09 New England Nuclear Corp Indium generator
US3620675A (en) * 1969-02-10 1971-11-16 Upjohn Co Apparatus for the measurement of dissolution rates
US3774036A (en) * 1972-02-23 1973-11-20 Searle & Co Generation of a supply of radionuclide
US3774035A (en) * 1971-07-12 1973-11-20 New England Nuclear Corp Method and system for generating and collecting a radionuclide eluate

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1432721A (fr) * 1965-02-10 1966-03-25 Saint Gobain Techn Nouvelles Dispositif pour la production de radio-éléments
FR1495454A (fr) * 1966-05-18 1967-09-22 Saint Gobain Techn Nouvelles Perfectionnements aux générateurs d'isotopes

Patent Citations (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2123212A (en) * 1933-09-28 1938-07-12 Scholler Heinrich Process of extraction
US2427042A (en) * 1946-04-03 1947-09-09 Gulf Research Development Co Method and apparatus for separating mixtures
US2968721A (en) * 1954-09-27 1961-01-17 Tracerlab Inc Methods of flow rate measurement
US3156532A (en) * 1961-06-30 1964-11-10 Robert F Doering Yttrium-90 generator
US3510271A (en) * 1963-04-11 1970-05-05 Pharmacia Fine Chem Inc Chromatographic separation employing a gel bed
US3561932A (en) * 1967-01-26 1971-02-09 New England Nuclear Corp Indium generator
US3535085A (en) * 1967-08-07 1970-10-20 Mallinckrodt Chemical Works Closed system generation and containerization of radioisotopes
US3620675A (en) * 1969-02-10 1971-11-16 Upjohn Co Apparatus for the measurement of dissolution rates
US3774035A (en) * 1971-07-12 1973-11-20 New England Nuclear Corp Method and system for generating and collecting a radionuclide eluate
US3774036A (en) * 1972-02-23 1973-11-20 Searle & Co Generation of a supply of radionuclide

Cited By (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4414145A (en) * 1979-04-17 1983-11-08 Byk-Millinkcrodt Cil B.V. Preparation and use of a 195M-AU-containing liquid
US4643891A (en) * 1979-04-17 1987-02-17 Mallinckrodt Diagnostica (Holland) B.V. Preparation and use of a 195m Au-containing liquid
US4472299A (en) * 1981-04-24 1984-09-18 Amersham International Plc Generator for radionuclide and process of use thereof
US4919900A (en) * 1987-01-21 1990-04-24 Aerospatiale Societe Nationale Industrielle System for crystal growth, particularly for space vessel
US5580541A (en) * 1991-05-01 1996-12-03 Mallinkrodt Medical, Inc. Method of conveying liquid materials and device for the automated elution of a radionuclidic generator
US5326532A (en) * 1993-02-25 1994-07-05 E. I. Du Pont De Nemours And Company Apparatus for chemically processing toxic materials
GB2382453A (en) * 2002-04-11 2003-05-28 Amersham Plc Radioisotope generator and method of construction thereof
GB2382453B (en) * 2002-04-11 2004-05-19 Amersham Plc Radioisotope generator and method of construction thereof
US20050253085A1 (en) * 2002-04-11 2005-11-17 Weisner Peter S Radiosotope generator and method of construction thereof
US7592605B2 (en) * 2002-04-11 2009-09-22 Ge Healthcare Limited Radioisotope generator and method of construction thereof
US20050278066A1 (en) * 2004-06-15 2005-12-15 Kevin Graves Automated dispensing system and associated method of use
US20080191148A1 (en) * 2005-08-09 2008-08-14 Gibson Chad M Radioisotope Generation System Having Partial Elution Capability
US20080224065A1 (en) * 2005-08-29 2008-09-18 Pollard Jr Ralph E System and Method for Eluting Radioisotope to a Container Disposed Outside of a Radioisotope Generator Assembly
EP3101659A1 (en) * 2006-10-06 2016-12-07 Mallinckrodt Nuclear Medicine LLC Self-aligning radioisotope elution system
EP3270383A1 (en) * 2006-10-06 2018-01-17 Mallinckrodt Nuclear Medicine LLC Self-aligning radioisotope elution system

Also Published As

Publication number Publication date
AU469264B2 (en) 1976-02-05
IL42812A0 (en) 1973-10-25
FR2194021B1 (US20110158925A1-20110630-C00042.png) 1976-11-12
FR2194021A1 (US20110158925A1-20110630-C00042.png) 1974-02-22
SU479307A3 (ru) 1975-07-30
JPS4957298A (US20110158925A1-20110630-C00042.png) 1974-06-04
IT992668B (it) 1975-09-30
AT335578B (de) 1977-03-25
BR7305651D0 (pt) 1974-08-22
BE802839A (fr) 1974-01-28
NL7310153A (US20110158925A1-20110630-C00042.png) 1974-01-29
IL42812A (en) 1976-03-31
AU5840673A (en) 1975-01-23
GB1428669A (en) 1976-03-17
ES417088A1 (es) 1976-03-16
ATA650473A (de) 1976-07-15
DD105392A5 (US20110158925A1-20110630-C00042.png) 1974-04-20
DE2236565A1 (de) 1974-02-07
ES417087A1 (es) 1976-03-16
DE2236565B2 (de) 1978-09-07
DE2236565C3 (de) 1979-05-03
CH559959A5 (US20110158925A1-20110630-C00042.png) 1975-03-14
ZA734837B (en) 1974-06-26

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