scholarly journals Magnesium-Molybate Compounds as Matrix for 99Mo/99mTc Generators

2011 ◽  
Vol 4 (2) ◽  
pp. 215-232 ◽  
Author(s):  
Fabiola Monroy-Guzman ◽  
Thania Susana Jimenez Martinez ◽  
Humberto Arriola ◽  
Luis Carlos Longoria Gandara
Keyword(s):  
99Mtc Generators

Fractionated elution of 99Mo/99mTc generators using calibrated vials

2018 ◽  
Vol 39 (9) ◽  
pp. 865-869
Author(s):  
Jonathan Vigne ◽  
Stéphane Emery ◽  
Nicolas Lemarie ◽  
Bénédicte Chavent ◽  
François Hallouard ◽  
...  
Keyword(s):  
99Mtc Generators

The utilization of 99Mo from “spent” 99Mo-99mTc generators

1976 ◽  
Vol 27 (3) ◽  
pp. 193-195 ◽  
Author(s):  
L.J. Kosarek ◽  
J.B. Martin ◽  
M.D. Otis
Keyword(s):  
99Mtc Generators

scholarly journals Gamma-ray spectrometric measurement of radionuclide purity of radiopharmaceuticals contained in bottle samples

2012 ◽  
Vol 27 (1) ◽  
pp. 13-19 ◽  
Author(s):  
Elio Tomarchio
Keyword(s):  
Gamma Ray ◽  
Diagnostic Information ◽  
Emission Tomography ◽  
Gamma Ray Spectrometry ◽  
Semiconductor Detectors ◽  
Radionuclide Purity ◽  
High Purity Germanium ◽  
Positron Emission ◽  
Measurement Geometry ◽  
99Mtc Generators

The radionuclide purity of a radiopharmaceutical product is usually measured by gamma-ray spectrometry with various measurement geometries. The importance of this test is that the radionuclide impurities, if present, result in an increase in the radiation dose to the patient without contributing to diagnostic information and in some cases may also interfere with the marking molecules and affect the proper conduct of diagnostic examination. In this work, gamma-ray spectrometry is used to determine the amounts of impurities by adopting as measurement geometry the same bottle containing eluted or prepared radiopharmaceuticals. In addition to high-purity germanium semiconductor detectors, the usefulness of NaI(Tl) and LaBr3(Ce) scintillators in routine operation is also examined. For the latter detectors, an evaluation of the minimum detectable activity was carried out and compared with the activity limits established by the regulation rules. The main cases considered are related to the first elution of 99Mo-99mTc generators and samples of 18F-FDG (fluoro-deoxy-glucose) to be used for positron emission tomography diagnostics.

Fission 99Mo/99mTc Generators – A Study of their Quality

1989 ◽  
Vol 28 (05) ◽  
pp. 201-207 ◽  
Author(s):  
E. Reich ◽  
K. W. Bögi
Keyword(s):  
Radiochemical Purity ◽  
Ph Value ◽  
Absorption Spectrometry ◽  
Aluminium Content ◽  
Federal Republic Of Germany ◽  
Reliable Source ◽  
Physical Examinations ◽  
A Site ◽  
Layer Chromatography ◽  
99Mtc Generators

Quality was controlled of seven different 99Mo/99mTc generators sold in the Federal Republic of Germany, which were all loaded with fission molybdenum. Aim of the work was to test the 99mTc eluates for their radionuclidic and radiochemical purity. Furthermore, the 99Mo content of the aluminium oxide column was measured. Determination of the elution efficiency, measurement of the pH-value of the eluate as well as a test to detect soluble aluminium in the eluate were also performed. In addition to the chemical and physical examinations, application, quality of accessories and their practicability were tested at all generators. The methods of analysis chosen were, among others, gamma spectrometry and thin-layer chromatography; the measuring methods were a site-sensitive proportional counter (measurement of the distribution of radioactivity of the chromatograms) and atomic absorption spectrometry (AI content of the eluates). The quality control of the 99mTc eluates had satisfying results. The eluates showed – with one exception – high and sufficient radionuclidic purity and very good radiochemical purity. A considerable overload of the columns with 99Mo at the time of reference was not found. The elution yields with values between 85 and 122% were in good agreement with the requirements. All eluates had pH-values between 5.0 and 6.5, and an aluminium content below 1 μg/ml. The generators had good performance and proved generally to be a reliable source of 99mTc-pertechnetate. The application was safe and, with some exceptions, fulfilled the requirements.

Analysis of the 89Sr and 90Sr Content in Eluates of Fission Produced 99Mo-99mTc Generators

1976 ◽  
Vol 30 (2) ◽  
pp. 179-182 ◽  
Author(s):  
Vincent J. Sodd ◽  
Donald L. Fortman
Keyword(s):  
90Sr Content ◽  
99Mtc Generators

Ruthenium Radioisotopes as Contaminants in Eluates from 99Mo-99mTc Generators

1978 ◽  
Vol 14 (11) ◽  
pp. 372-374
Author(s):  
J. Vlček ◽  
V. Hušák ◽  
J. Roháček ◽  
V. Rusek
Keyword(s):  
99Mtc Generators

Rapid estmation of technetium in99Mo−99mTc generators

1979 ◽  
Vol 52 (2) ◽  
pp. 471-475 ◽  
Author(s):  
J. Alvarez ◽  
F. Cortés ◽  
T. Pérez
Keyword(s):  
99Mtc Generators
Sign in / Sign up

Export Citation Format

Share Document