“…The MCNP4A (Briesmeister, 1993) radiation transport code is applied to perform the calculations in this work and it is a general purpose, 3D general geometry, time-dependent code, which is used to calculate coupled neutron-photon-electron transport in bulk samples. As many as 15,00,000 histories were run in order to produce reliable confidence intervals (Eshwarappa et al, 2007). The MCNP plot of the target geometry is shown in Fig.…”