Simulation and Performance of 99Mo/99mTc Radioisotope Separation by Modified Extraction Method

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. © Published under licence by IOP Publishing Ltd.