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
• • 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

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• the user may withdrawn the desired radioisotope from the generator respectively.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.

Landscapes

• 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)

Applications Claiming Priority (1)

Publications (1)

Family

ID=19812592

Family Applications (1)

Country Status (11)

Cited By (10)

Families Citing this family (2)

Family Cites Families (4)

• 1971
  • 1971-03-02 NL NL7102716.A patent/NL165321C/xx not_active IP Right Cessation
• 1972
  • 1972-02-17 DE DE2207309A patent/DE2207309C3/de not_active Expired
  • 1972-02-28 JP JP1975872A patent/JPS544039B1/ja active Pending
  • 1972-02-28 FR FR7206671A patent/FR2128373B1/fr not_active Expired
  • 1972-02-28 SE SE7202432A patent/SE387768B/xx unknown
  • 1972-02-28 IT IT21138/72A patent/IT947968B/it active
  • 1972-02-28 GB GB900772A patent/GB1353293A/en not_active Expired
  • 1972-02-28 CA CA135,683A patent/CA971749A/en not_active Expired
  • 1972-02-28 CH CH279272A patent/CH578235A5/xx not_active IP Right Cessation
  • 1972-02-29 US US00230502A patent/US3785990A/en not_active Expired - Lifetime
  • 1972-02-29 BE BE780010A patent/BE780010A/xx not_active IP Right Cessation

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