mcnp2.6 code

The 43Sc radioisotope with a half-life of 3.891 h is an ideal radioisotope for PET imaging. In this paper, the production of 43Sc radioisotope through 43Ca(p,n)43Sc, 44Ca(p,2n)43Sc, 42Ca(d,n)43Sc, 43Ca(d,2n)43Sc, 40Ca(α,p)43Sc and 41K(α,2n)43Sc nuclear reactions have been investigated. The cross-section of these reactions was calculated using the TALYS1.8 and ALICE ASH 1.0 nuclear codes and compared with the experimental results. The SRIM-2013 and MCNPX2.6 codes are used to calculate the stopping power and projectile flux distribution in the target. The theoretical and simulation production yields for each reaction are calculated. The production yield results of some of these reactions are compared with the experimental results at the same optimum energy interval, which shows relatively good agreement between the experimental and computational results.