The radionuclide purity of a radiopharmaceutical product is usually measured by gamma-rayspectrometry 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. Inaddition 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.
|Numero di pagine||7|
|Rivista||NUCLEAR TECHNOLOGY & RADIATION PROTECTION|
|Volume||Vol. 27 No. 1|
|Stato di pubblicazione||Published - 2012|
All Science Journal Classification (ASJC) codes
- Nuclear Energy and Engineering
- Safety, Risk, Reliability and Quality