New design of thermal neutron flux distribution of Am–Be neutron source irradiation in the paraffin moderator using MCNP-6

Abstract

to increase the neutron flux Americium-Beryllium activity 20 Ci, source is centric to the center in a paraffin castle, our study is proposed a design prototype of the source, which has two parallel barriers beryllium, for to increase the radial flux from the source, fast neutrons are slowed in paraffin we used Monte Carlo code MCNP-6 for simulation, results analysis and was found with interpreting graphs is compared with other studies, we noticed that the neutron flux increasing  (2.2 ± 0.0007) × 10⁶ n/cm²s, this result is more improved than previous studies.