Improved MCNP Simulation Considering Neutron Angular Distribution and its Experimental Verification

Abstract

Adeuterium-deuterium (DD) neutron generator has been simulated with MCNP 6.2. Two methods of simulating the emission of the neutrons created by the generator have been utilized: One with an isotropic emission of resultant neutrons and a second (anisotropic) accounting for the angular and energy distribution of resultant neutrons. The isotripic source was simulated using data generated by the DROSG-2000 program. A series of gold foils were irradiated at three different geometries around the neutron generator and the results compared to those produced from the two simulation methods. At zero degrees in the laboratory frame, both methods of simulation were shown to be equally valid. As the irradiation angles deviated from zero degrees, the anisotropic simulation method maintained accuracy while the isotropic simulation increased in error.