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

[+] Author Affiliations
T. Kakavand, R. Ghasemi

Zanjan University, Zanjan, Iran

K. Kamali Moghaddam, M. Sadeghi

NRCAM, Tehran, Iran

Paper No. ICONE14-89667, pp. 461-466; 6 pages
doi:10.1115/ICONE14-89667
From:
  • 14th International Conference on Nuclear Engineering
  • Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy
  • Miami, Florida, USA, July 17–20, 2006
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-4244-4 | eISBN: 0-7918-3783-1
  • Copyright © 2006 by ASME

abstract

Iodine-123 is one of the most famous radioisotopes for Single Photon Emission Computed Tomography (SPECT) use, so, for 123 I production, the 123 Te has been chosen as a target through 123 Te (p,n) 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 & SRIM and doing a sort of calculations, we are going to demonstrate our latest effort for feasibility study of producing 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 123 I has been calculated by analytical methods. Our prediction for producing 123 I yield via bombardment of 123 Te (%99.9) with proton beam energy at 5–15 MeV is about 7.2 mCi/μAh. The present work shows that, the 123 I yield is proportional to abundance of 123 Te. 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.

Copyright © 2006 by ASME

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