title: Prediction of 67Ga production using the Monte Carlo code MCNPX.
abstract: The widely used Monte Carlo simulation code Monte Carlo N-Particle System (MCNPX) has been utilized to simulate the production of (67)Gallium via multiple nuclear reaction channels. Based on the MCNPX-generated, energy-dependent proton flux within a Zn target during irradiation, the (67)Ga 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.
authors.affiliation: Agricultural, Medical and Industrial Research School, Nuclear Science and Technology Research Institute, P.O. Box: 31485/498, Karaj, Iran. msadeghi@nrcam.org
authors.forename: M
authors.initials: M
authors.lastname: Sadeghi
authors.forename: N
authors.initials: N
authors.lastname: Jokar
authors.forename: T
authors.initials: T
authors.lastname: Kakavand
authors.forename: H
authors.initials: H
authors.lastname: Ghafoori Fard
authors.forename: C
authors.initials: C
authors.lastname: Tenreiro
mesh_terms: D003198:Computer Simulation; D005710:Gallium Radioisotopes / Q000032:analysis* / Q000737:chemistry*; D007553:Isotope Labeling / Q000379:methods; D008422:Materials Testing / Q000379:methods; D008956:Models, Chemical; D015233:Models, Statistical; D009010:Monte Carlo Method; D011874:Radiometry / Q000379:methods*; D012984:Software
chemical_list: D005710:Gallium Radioisotopes