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Results for “Radionuclide Generators”

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At least 19 recordsLinked to original sources
PubMed1992

Development of a high performance zinc-62/copper-62 radionuclide generator for positron emission tomography.

Clinical utilisation of positron emission tomography could be enhanced by the availability of short-lived radionuclides derived from generator systems. The zinc-62/copper-62 combination is one such system which could be used as a source for a number of copper-62 radiopharmaceuticals. We have developed and optimised a high activity (5.6 GBq, 150 mCi) zinc-62/copper-62 generator to provide 62Cu in a form that is suitable for direct labelling of pyruvaldehyde-bis-(N4-methylthiosemicarbazone)-copper(II), Cu(PTSM). The distribution coefficients of Zn(II) and Cu(II) between anion-exchange resin and various hydrochloric acid/organic solvent mixtures were measured. Based on these measurements a generator eluent of 0.3 M HCl/40% ethanol provided 62Cu in greater than 90% yield in a 3-ml volume. A very low 62Zn breakthrough of less than 3 x 10(-7)% was achieved. Copper-PTSM was successfully labelled with the no-carrier-added 62Cu eluent directly from the generator with 94% radiochemical yield.

Copper↗
PubMed1977

Microbial contamination of radionuclide generators.

Technetium-99m generators were grossly contaminted using 5 different strains of microorganisms. Elution of the generators showed that the number of microorganisms was reduced by a factor of 10(4)-10(6). There were no indications that the generators would support bacterial growth. It is concluded that it would be acceptable from a microbiologic point of view to omit autoclaving and membrane filtration of the final product provided that proper aseptic techniques are applied.

Bacteria↗
PubMed1977

An improved 191Os-191mIr generator for radionuclide angiocardiography.

191mIr is a useful tracer for radionuclide angiocardiography and may be of particular value in the evaluation of heart disease in children. It has a short half-life, a suitable photon energy, and may be obtained as a generator product by decay of its long-lived parent 191Os. A 191Os-191mIr generator capable of providing at least 18 mCi of 191mIr in 1.5 ml of eluant is described. 191mIr is separated from 191Os by absorbing 191OsCl6(-2) on an ion exchange resin and eluting with a solution of 8.7% NaCl at a pH of 2.2. The generator employs an additional resin column which is replaced to minimize 191Os breakthrough.

Animals↗
PubMed1992

Cyclotrons and positron emission tomography radiopharmaceuticals for clinical imaging.

Positron emission tomography (PET) requires positron-emitting radionuclides that emit 511-keV photons detectable by PET imagers. Positron-emitting radionuclides are commonly produced in charged particle accelerators, eg, linear accelerators or cyclotrons. The most widely available radiopharmaceuticals for PET imaging are carbon-11-, nitrogen-13-, and oxygen-15-labeled compounds, many of which, either in their normal state or incorporated in other compounds, serve as physiological tracers. Other useful PET radiopharmaceuticals include fluorine-18-, bromine-75-, gallium-68 (68Ga)-, rubidium-82 (82Rb)-, and copper-62 (62Cu)-labeled compounds. Many positron emitters have short half-lives and thus require on-site cyclotrons for application, and others (68Ga, 82Rb, and 62Cu) are available from radionuclides generators using relatively long-lived parent radionuclides. This review is divided into two sections: cyclotrons and PET radiopharmaceuticals for clinical imaging. In the cyclotron section, the principle of operation of the cyclotron, types of cyclotrons, medical cyclotrons, and production of radionuclides are discussed. In the section on PET radiopharmaceuticals, the synthesis and clinical use of PET radiopharmaceuticals are described.

Brain↗
PubMed1979

Potential column chromatography generators for ionic Ga-68. I. Inorganic substrates.

Chemical separations for Ga-68 from Ge-68 using adsorption chromatography on inorganic materials are described. The adsorbents used were TiO2, ZrO2, and SiO2. Distribution coefficients for Ge and Ga on these absorbents were determined as a function of reagent concentration and duration of equilibration. The distribution coefficient (w/w) for Ge on SiO2 reached 250 in 6 N HNO3, whereas Ga was no significantly adsorbed. Therefore, Ga-68 can be collected with a mall volume of 6 N HNO3 eluent. By contrast, large volumes of 1 N HNO3 were necessary to collect Ga-68 from ZrO2, since the KD of Ga under these circumstances was about 50. The Ga-68 eluted from TiO2 was chemically contaminated with titanates and would require additional chemical manipulation in order to make it injectable. All the adsorbents could lead to chromatographic systems that would allow acceptable chemical separations. However, the specific requirements for a radionuclide generator, usable in a hospital environment, make the SiO2-based system the most attractive.

Chromatography↗
PubMed1992

Cross sections of natSb(p,x) reactions for 30-46 MeV protons.

In order to optimize the production of 118Te in thick targets for use in a 118Te/118Sb radionuclide generator, the excitation function for the 121Sb(p,4n)118Te reaction has been measured for 30-46 MeV protons. The excitation functions for the competing reactions natSb(p,xn)119mTe, natSb(p,xn)119Te, natSb(p,xn)121mTe, natSb(p,pxn)120mSb and 123Sb(p,pn)122Sb have also been determined using stacked foil techniques. The 121Sb(p,4n)118Te reaction cross section maximum was found to be 480 mbarn at 44 MeV. In order to minimize the 119m + 119Te interference a minimum proton beam energy of 40 MeV is required. The cross section results are compared with published data and with calculated excitation functions.

Antimony↗
PubMed1975

Generator-produced 99m TcO4-: carrier free.

A solution of 99m-TCO4-minus, as eluted from a 99Mo-99mTc radionuclide generator contains a greater chemical quantity of technetium than that attributable to the metastable isomer alone. The isomeric transition of the radionuclide of interest, 99mTc, gives rise to a determinable and chemically significant quantity of technetium carrier, 99Tc. A method is presented for calculating the total chemical quantity of technetium in a generator eluate.

Molybdenum↗
PubMed1978

Krypton-81m.

Explore the source record for details and available documents.

Computers↗
PubMed1978

Analysis of wall motion abnormalities of the heart and great vessels by computer generated cine-radionuclide-equilibrium study.

Cardiac wall motion was evaluated in 54 patients by ECG-gated blood pool scintigraphy (GBPS) and computer assisted cine-radionuclide-equilibrium study (CRES). The cine format in CRES enhances the subtle aspects of great vessel and cardiac chamber motion and volume abnormalities. An off-line system using a general purpose computer permitted CRES to be initiated in smaller nuclear medicine facilities without large financial investiments.

Adult↗
PubMed1979

Evaluation and application of alumina-based Rb-82 generators charged with high levels of Sr-82/85.

Generator-produced Rb-82, a 75-sec positron emitter with potential for myocardial blood-flow imaging, was studied with various ion-exchange columns to evaluate the characteristics of alumina as an adsorber for the 25-day Sr-82 parent. Test columns of alumina, Bio Rex 70, and Chelex 100 were loaded with multimillicurie amounts of no-carrier-added Sr-82/Sr-85 (Sr-85 is a production contaminant). The breakthrough of Sr-82/Sr-85, and the yield of Rb-82, were determined for long-term elutions from each column with up to 4 liter of 2% NaCl solution at pH 8 to 9. The breakthrough of Sr-82/85 was 10(-6)-10(-5) from aluminal 10(-6)-10(-4) from Chelex 100 and Bio Rex 70. The effects of eluent flow rate and concentration, and of alumina volume, on the breakthrough and yield were also studied. An improved and automated Rb-82 generator was used for myocardial and brain blood-flow studies in experimental animals and in man; it was equipped with solenoid flow-control valves and five in. of lead shielding for the alumina columns, which were charged with 25-50 mCi Sr-82 (100-150 mCi Sr-85). The Rb-82 generator with alumina column provided up to 20-40 mCi of Rb-82 as often as every 5-10 min with less than 10(-5) breakthrough of Sr-82/85 over the 2- to 3-mo, useful life of the generator.

Aluminum Oxide↗