Abstract
Production of radioisotopes which are required in the fields such as medicine, industry, agriculture, etc. is one of the main utilizations of Dhruva reactor apart from neutron beam-based basic scientific research. Sm153 and Lu177 are among the important medical radioisotopes being produced at Dhruva. In the present study, we have estimated the total and specific activities built up in the irradiated samples (15 mg Sm2O3 with 98.4% enrichment of Sm152 and 500 μg LuCl3 with 85% enrichment of Lu176) as a function of irradiation time. The optimum irradiation time for achieving maximum specific activity of desired radioisotope is found. Calculations are done for the maximum neutron flux (2.0 × 1014 n/cm2/s) available at the tray rod location. Contributions of thermal as well as epithermal neutrons are considered. Europium impurity is also estimated in the activated Samarium sample. Assessment of safety-related parameters such as nuclear heating, reactivity load, and shield thickness is also discussed.
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