Abstract Technetium-99m (99mTc) is a nuclide in nuclear medicine, commonly derived as a decay product from molybdenum-99 (99Mo). Unfortunately, Japan and Indonesia rely entirely on imports for their 99Mo/99mTc supply. This study aims to determine the distribution coefficient (Kd) for the 99Mo/99mTc production process and assess the efficiency of Methyl Ethyl Ketone (MEK) as a solvent in the extraction process. The method Initial tests using Rhenium (Re) as a substitute for 99mTc, conducted in collaboration with the Japan Atomic Energy Agency (JAEA), revealed optimal conditions: a standing time of 5 to 15 minutes, a mixing time of 3 minutes with a motor speed of 250 rpm, and a MEK volume exceeding 20 ml. These conditions yielded a Re extraction efficiency exceeding 85.14%, with a Re elution yield of up to 98.73%. These findings served as a database for experiments involving 99Mo/99mTc conducted at the National Research and Innovation Agency (BRIN). In hot experiments, the 99mTc recovery rate through MEK exceeded 100%, while the elution process achieved a recovery rate of 97.81%. Through simulation and facility enhancements in the hot cell, the 99mTc extraction recovery increased to 44.86%, and elution recovery ranged from 90.62%. From the calculation results, the distribution coefficient value database (Kd-99mTc) was 0.45. Radionuclide and radiochemistry purity of the 99mTc solution were assessed using the Gamma Spectrometer and TLC Scanner, resulting in purity of 99.90% and 99.80%, respectively. These results underscore the potential for domestic production 99mTc, reducing reliance on imports.
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