US3785990A - Method of manufacturing a generator which produces radio-isotopes and has an improved elution efficiency,and generator obtained by this method - Google Patents

Method of manufacturing a generator which produces radio-isotopes and has an improved elution efficiency,and generator obtained by this method Download PDF

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Publication number
US3785990A
US3785990A US00230502A US3785990DA US3785990A US 3785990 A US3785990 A US 3785990A US 00230502 A US00230502 A US 00230502A US 3785990D A US3785990D A US 3785990DA US 3785990 A US3785990 A US 3785990A
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United States
Prior art keywords
generator
adsorbent
oxidant
isotope
salt solution
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Expired - Lifetime
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US00230502A
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English (en)
Inventor
H Benjamins
Finda H Panek
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MAALLINCKRODT DIAGNOSTICA (HOLLAND) BV WESTERDUINWEG 3 1755 LE PETTEN NETHERLANDS
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Assigned to MAALLINCKRODT DIAGNOSTICA (HOLLAND) B.V., WESTERDUINWEG 3, 1755 LE PETTEN, THE NETHERLANDS reassignment MAALLINCKRODT DIAGNOSTICA (HOLLAND) B.V., WESTERDUINWEG 3, 1755 LE PETTEN, THE NETHERLANDS CHANGE OF NAME (SEE DOCUMENT FOR DETAILS). EFFECTIVE DATE: SEPTEMBER 3, 1984 Assignors: BYK-MALLINCKRODT CIL B.V.
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Expired - Lifetime legal-status Critical Current

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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21GCONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
    • G21G4/00Radioactive sources
    • G21G4/04Radioactive sources other than neutron sources
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21GCONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
    • G21G1/00Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
    • G21G1/0005Isotope delivery systems

Definitions

  • the invention relates to a method of manufacturing a generator which produces radioisotopes.
  • Radionuclides having a half-life of a few hours to a few days are used in medicine for diagnostic purposes.
  • radionuclides which are pure gamma radiators.
  • the optimum gamma lines lie between 100 and 400 kev.
  • This radio-active technetium isotope may be used for the above indicated purpose as such but it is also suitable to label other substances such, for example, as albumins.
  • the radioisotope suitable for medical use is obtained inter alia from a generator, which frequently is referred to as a cow or milker.
  • the radioisotope then is marketed in the form of the generator.
  • the user may withdrawn the desired radioisotope from the generator respectively.
  • Such instantaneous production is of great practical importance because of the rapid decay of a suitable radioisotope.
  • An isotope generator is obtainable by filling a container provided with an inlet and an outlet with an adsorbent material to which a radioactive parent isotope is then applied. If desired, the generator may be provided with seals which permit sterile use of the generator (Netherlands patent application No. 6,607,699, PHN. 1670).
  • a frequently used adsorbent is A1 0
  • an adsorbent largely consisting of A1 0 is used in producing the aforementioned Tc generator.
  • the radioactive parent isotope present on the adsorbent by its decay produces the daughter isotope, which is of interest for medical purpose, with the emission of radiation.
  • radioactive molybdenum in the form of a molybdate is used as the parent isotope.
  • the Tc produced from M0 by radioactive decay will mainly be in the form of the pertechnetate.
  • a washing liquid or eluent is admitted at the top through the inlet.
  • the eluent traverse the adsorbent and carries along the radioactive daughter isotope present.
  • the eluent together with the radioactive daughter isotope dissolved in it leaves the generator at the bottom and is collected in a receiver which if desired may be rigidly secured to the generator proper.
  • the parent isotope is hardly, or not at all, displaced over the adsorbent by the eluent.
  • a suitable eluent is an isotonic salt solution such, for example, as a 0.9% common salt solution.
  • the proposed step of improving the efiiciency has to be taken by the user of the generator himself.
  • the said degeneration may be greatly reduced or even prevented if at least at the regions in the generator in which there is strong radiation the generator system it brought into an oxidizing condition.
  • the invention relates to a method of manufacturing an isotope generator in which a container provided with an inlet and an outlet is filled with an adsorbent mainly consisting of A1 to which a radioactive parent isotope is applied, and the invention is characterized in that even before first use of the generator the adsorbent is brought to an oxidizing condition by the application of an oxidant.
  • the oxidant to be used according to the invention preferably should have a strong aflinity to the A1 0 adsorbent, for it is important that when the generator manufactured by the method according to the invention is used the washing agent used should not remove the oxidant from the adsorbent, but on the contrary it forms part of the substance of the invention that the oxidant is fixed as securely as possible in the region of the radiation field, i.e. of the parent isotope.
  • the application of the oxidant may be effected by a known method.
  • a solution of the oxidant is used.
  • the solvent may be removed from the adsorbent, for example by drawing off at a reduced pressure.
  • water or an aqueous salt solution is used as the solvent it need not be removed from the adsorbent.
  • the amount of oxidant to be applied depends on various factors. Some of these factors are the radioactivity level and the shape of the generator, the position of the parent isotope on the adsorbent, the concentration of the oxidant in the solution used and the nature of the oxidant.
  • the treatment with the oxidant may be effected either before or after sterilization.
  • the pH of the solution was 1 to 2.
  • Do. 29..- 1 mg. K2CrzO7 in 1 ml. of salt solution Do. 30.... -do Do.
  • Table II shows that the elution efficiency of the generators 25 to 30 which contain a comparatively small amount of oxidant is appreciably lower than that of the generators 1-24 which contain larger amounts of oxidant.
  • the reference generator without oxidant gives a very poor yield.
  • the table shows that at the twelfth elution the difierences in elution efliciency are substantially eliminated. This may readily be explained by considering that at the twelfth elution the radioactivity of the generators, which initially was 300 mCi, had fallen to an extent such that the limit value below which the influence of the radiation on the etficiency is absent or at least greatly reduced is passed.
  • an isotope generator in which a container provided with an inlet and outlet is filled with an adsorbent consisting mainly of A1 0 to which adsorbent a radioactive parent isotope is applied, the improvement which comprises bringing the adsorbent to an oxidizing condition by applying to the adsorbent an oxidant which is strongly bound to the adsorbent prior to the first elution.

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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)
  • Medicines Containing Antibodies Or Antigens For Use As Internal Diagnostic Agents (AREA)
  • Solid-Sorbent Or Filter-Aiding Compositions (AREA)
US00230502A 1971-03-02 1972-02-29 Method of manufacturing a generator which produces radio-isotopes and has an improved elution efficiency,and generator obtained by this method Expired - Lifetime US3785990A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
NL7102716.A NL165321C (nl) 1971-03-02 1971-03-02 Werkwijze voor de vervaardiging van een radio-isotopen producerende generator.

Publications (1)

Publication Number Publication Date
US3785990A true US3785990A (en) 1974-01-15

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ID=19812592

Family Applications (1)

Application Number Title Priority Date Filing Date
US00230502A Expired - Lifetime US3785990A (en) 1971-03-02 1972-02-29 Method of manufacturing a generator which produces radio-isotopes and has an improved elution efficiency,and generator obtained by this method

Country Status (11)

Country Link
US (1) US3785990A (xx)
JP (1) JPS544039B1 (xx)
BE (1) BE780010A (xx)
CA (1) CA971749A (xx)
CH (1) CH578235A5 (xx)
DE (1) DE2207309C3 (xx)
FR (1) FR2128373B1 (xx)
GB (1) GB1353293A (xx)
IT (1) IT947968B (xx)
NL (1) NL165321C (xx)
SE (1) SE387768B (xx)

Cited By (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3902849A (en) * 1971-08-19 1975-09-02 Medi Physics Inc Radioisotope and radiopharmaceutical generators
US3970583A (en) * 1973-02-20 1976-07-20 U.S. Philips Corporation Isotope generator provided with a carrier material which in addition to Al2 O3 contains fully or partly hydrated MnO2
US4010109A (en) * 1973-07-02 1977-03-01 Kurt Sauerwein Device for marking fluent materials
US4041317A (en) * 1976-05-19 1977-08-09 E. R. Squibb & Sons, Inc. Multiple pH alumina columns for molybdenum-99/technetium-99m generators
US4206358A (en) * 1977-10-19 1980-06-03 Australian Atomic Energy Commission Technetium-99 generators
US4280053A (en) * 1977-06-10 1981-07-21 Australian Atomic Energy Commission Technetium-99m generators
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
US20030219366A1 (en) * 2002-04-12 2003-11-27 Horwitz E. Philip Multicolumn selectivity inversion generator for production of ultrapure radionuclides
US20080226543A1 (en) * 2005-03-24 2008-09-18 Nigel John Osborn Stripping Method

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2443030C2 (ru) * 2010-02-03 2012-02-20 Федеральное государственное унитарное предприятие "Ордена Трудового Красного Знамени научно-исследовательский физико-химический институт им. Л.Я. Карпова" (ФГУП "НИФХИ им. Л.Я. Карпова") ГЕНЕРАТОР ТЕХНЕЦИЯ-99m С СУЛЬФО-КАРБОКСИЛИРОВАННЫМ КАТИОНООБМЕННЫМ ЗАЩИТНЫМ СЛОЕМ И СПОСОБ ЕГО ПОЛУЧЕНИЯ

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3382152A (en) * 1964-09-28 1968-05-07 Union Carbide Corp Production of high purity radioactive isotopes
NL6607699A (xx) * 1966-06-03 1967-12-04
US3468808A (en) * 1967-06-16 1969-09-23 Union Carbide Corp Production of high purity radioactive technetium-99m
US3664964A (en) * 1968-07-03 1972-05-23 Squibb & Sons Inc Eluent for radioisotopes

Cited By (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3902849A (en) * 1971-08-19 1975-09-02 Medi Physics Inc Radioisotope and radiopharmaceutical generators
US3970583A (en) * 1973-02-20 1976-07-20 U.S. Philips Corporation Isotope generator provided with a carrier material which in addition to Al2 O3 contains fully or partly hydrated MnO2
US4010109A (en) * 1973-07-02 1977-03-01 Kurt Sauerwein Device for marking fluent materials
US4041317A (en) * 1976-05-19 1977-08-09 E. R. Squibb & Sons, Inc. Multiple pH alumina columns for molybdenum-99/technetium-99m generators
US4280053A (en) * 1977-06-10 1981-07-21 Australian Atomic Energy Commission Technetium-99m generators
US4206358A (en) * 1977-10-19 1980-06-03 Australian Atomic Energy Commission Technetium-99 generators
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
US20030219366A1 (en) * 2002-04-12 2003-11-27 Horwitz E. Philip Multicolumn selectivity inversion generator for production of ultrapure radionuclides
US6998052B2 (en) 2002-04-12 2006-02-14 Pg Research Foundation Multicolumn selectivity inversion generator for production of ultrapure radionuclides
US20080226543A1 (en) * 2005-03-24 2008-09-18 Nigel John Osborn Stripping Method
US8053622B2 (en) 2005-03-24 2011-11-08 Ge Healthcare Limited Stripping method

Also Published As

Publication number Publication date
DE2207309C3 (de) 1981-07-30
CA971749A (en) 1975-07-29
JPS544039B1 (xx) 1979-03-01
NL165321B (nl) 1980-10-15
DE2207309B2 (de) 1980-11-20
NL165321C (nl) 1981-03-16
DE2207309A1 (de) 1972-09-07
SE387768B (sv) 1976-09-13
FR2128373B1 (xx) 1983-04-08
GB1353293A (en) 1974-05-15
FR2128373A1 (xx) 1972-10-20
NL7102716A (xx) 1972-09-05
IT947968B (it) 1973-05-30
CH578235A5 (xx) 1976-07-30
BE780010A (fr) 1972-08-29

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AS Assignment

Owner name: MAALLINCKRODT DIAGNOSTICA (HOLLAND) B.V., WESTERDU

Free format text: CHANGE OF NAME;ASSIGNOR:BYK-MALLINCKRODT CIL B.V.;REEL/FRAME:004466/0151

Effective date: 19850728