Shielding studies for 2.5 MeV neutrons using GEANT4
ORAL
Abstract
By means of the software GEANT4, a toolkit based on the Monte Carlo method, we seek to study the dispersive effects that 2.5 MeV neutrons have, as well the gamma-yield, after interacting with various attenuating materials with simple geometrical configurations. A simulated mass of Uranium-238 is considered in the study with the purpose of observing the behavior of its characteristic yield after fast neutron irradiation.
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