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

Conference ·
OSTI ID:20995597
;  [1]; ;  [2]
  1. Zanjan University, Zanjan (Iran, Islamic Republic of)
  2. Nuclear Research Center for Agriculture and Medicine - NRCAM, AEOI, P.O. Box 31585-4395, Karaj (Iran, Islamic Republic of)
Iodine-123 is one of the most famous radioisotopes for Single Photon Emission Computed Tomography (SPECT) use, so, for {sup 123}I production, the {sup 123}Te has been chosen as a target through {sup 123}Te (p,n) {sup 123}I 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 and SRIM and doing a sort of calculations, we are going to demonstrate our latest effort for feasibility study of producing {sup 123}I 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 {sup 123}I has been calculated by analytical methods. Our prediction for producing {sup 123}I yield via bombardment of {sup 123}Te (%99.9) with proton beam energy at 5-15 MeV is about 7.2 mCi/{mu}Ah. The present work shows that, the {sup 123}I yield is proportional to abundance of {sup 123}Te. Thermodynamical calculations with various current beams of up to 900 {mu}A have been done, and the proper cooling system for the above purpose has been designed. (authors)
Research Organization:
The ASME Foundation, Inc., Three Park Avenue, New York, NY 10016-5990 (United States)
OSTI ID:
20995597
Country of Publication:
United States
Language:
English