Design of Tellurium-123 Target for Producing Iodine-123 Radioisotope Using Computer Simulation Techniques

Iodine-123 is one of the most famous radioisotopes for Single Photon Emission Computed Tomography (SPECT) use, so, for ¹²³I production, the ¹²³Te has been chosen as a target through ¹²³Te (p,n) ¹²³I reaction. The various enriched targets (%99.9, %91, %85.4 and %70.1) have been used for the present calculations. In the current work, by using computer codes; ALICE & SRIM and doing a sort of calculations, we are going to demonstrate our latest effort for feasibility study of producing ¹²³I by the above mentioned reaction. By using proton beam energy of less than 30 MeV, the mentioned codes give more accurate results. The cross section of all Tellurium reactions with proton has been calculated at 0–30 MeV proton beam energy with ALICE code. In the present work, the yield of ¹²³I has been calculated by analytical methods. Our prediction for producing ¹²³I yield via bombardment of ¹²³Te (%99.9) with proton beam energy at 5–15 MeV is about 7.2 mCi/μAh. The present work shows that, the ¹²³I yield is proportional to abundance of ¹²³Te. Thermodynamical calculations with various current beams of up to 900 μA have been done, and the proper cooling system for the above purpose has been designed.