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Prediction of 67Ga production using the Monte Carlo code MCNPX

Prediction of 67Ga production using the Monte Carlo code MCNPX

Authors :
Claudio Tenreiro
Tayeb Kakavand
H. Ghafoori Fard
N. Jokar
Mahdi Sadeghi
Source :
Applied Radiation and Isotopes. 77:14-17
Publication Year :
2013
Publisher :
Elsevier BV, 2013.

Abstract

The widely used Monte Carlo simulation code Monte Carlo N-Particle System (MCNPX) has been utilized to simulate the production of 67Gallium via multiple nuclear reaction channels. Based on the MCNPX-generated, energy-dependent proton flux within a Zn target during irradiation, the 67Ga production yield was determined. Theoretical calculations of the production yield using the stopping power from the SRIM (stopping and range of ions in matter) code were compared to the measurements from the MCNPX code. These results were in good agreement with reported data, thus confirming the usefulness and accuracy of MCNPX as a tool for the design and optimization of targets for the production of other radionuclides.

Details

ISSN :
09698043
Volume :
77
Database :
OpenAIRE
Journal :
Applied Radiation and Isotopes
Accession number :
edsair.doi.dedup.....457af50bceaeb4bd331817b1e20e90c6
Full Text :
https://doi.org/10.1016/j.apradiso.2013.02.001