Abstract
Abstract The medical radionuclide 99mTc is the most widely used type of radionuclide in the field of nuclear medicine. 99mTc is the decay product of 99Mo. One of the quality control parameters of 99mTc is the 99Mo breakthrough limit. It is important to know the 99Mo breakthrough so that the quality of 99mTc produced can be optimal for diagnosis in nuclear medicine. This study aims to verify the 99Mo breakthrough activity from a non-fission 99Mo/99mTc generator whether they meet the established international limit standard. This research used a non-fission 99Mo/99mTc generator produced in multipurpose reactor G.A. Siwabessy, Indonesia. Gamma Spectrometer measurement of 99Mo and two 5 mL liquid standard sources of mix 133Ba and 152Eu used the same geometry. First standard as a calibration and efficiency identification function while the second standard is used to verify the measurement each at 3, 5, 7, 9 and 11 cm source to detector distance respectively. The 99Mo breakthrough activity (µCi) then devided to the activity of 99mTc (mCi) for the six eluted product from each days elution process of the generator. The results obtained showed that the 99Mo elution in the first elution had the highest breakthrough of 0.233 uCi 99Mo /mCi 99mTc, which exceeded the set limit of 0.15 uCi 99Mo /mCi 99mTc. While in the second, third, fourth, and fifth elution still have the 99Mo breakthrough, but these breakthrough did not exceed the limit and met one of the requirements of the 99mTc medical radionuclide parameter.
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