The MCNP code based on the Monte Carlo model is intended for neutron simulations. It is used to study neutron production, neutron flux calculations, energy deposition, dose, and multiplicity of… Click to show full abstract
The MCNP code based on the Monte Carlo model is intended for neutron simulations. It is used to study neutron production, neutron flux calculations, energy deposition, dose, and multiplicity of neutrons; in this paper, we used the MCNP6 code for neutron simulation in spallation targets. We are interested in a 1 GeV proton beam that enters frontal impact with several targets; the geometry of all targets is 10 cm in height and 69 cm in radius. The simulations made in this study clearly show that there are no heavy targets (Co, Cd and Fe), but their neutron production rates are remarkable. We also conclude that the selected targets may be useful to handle almost like spallation targets in an accelerator-driven system.
               
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