Monte Carlo transport code using for simulating the neutron yield of spallation targets: Uranium, Thorium, and Tantalum are used for an accelerator based on high proton beam

Abstract

There are several heavy materials used as neutron spallation targets. The purpose of this study is to optimize the geometry of the neutron production target in the spallation process. using Monte-Carlo method-Particle code MCNP-6. The simulation includes Uranium, Thorium, and Tantalum targets. We investigated the flux of neutron produced as well as the neutron axial distribution by variation the spallation target, target height and proton beam energy. The proton beams of a 2 cm radius were assumed uniformly distributed.