Monte Carlo Computational Simulation of Neutron Activation of Materials Lam, Y. W.author Wong, C. S.author Ratnavelu, K.authorA Monte Carlo computational simulation technique is implemented in GEANT4 object-oriented architecture with ENDF/B VI cross section data. It is used to describe the attenuation and activation of neutron with various materials (lead, aluminium, lithium and ethanol). The neutron inelastic, elastic and capture processes will be considered in the simulation. The simulated cross sections are compared with the Breit-Wigner distribution, which is used in ENDF/B VI and gamma (γ) energy spectrum of materials will be cumulated as the basic data for material identification.Q Science, Computer Science2003-12Malaysian Institute of Physics (IFM)Journal