Experimental neutron attenuation measurements in possible fast reactor shield materials

Neutron attenuation properties of shield materials that have prospective use in fast reactors have been studied in this research. Activation foils were employed to study neutron attenuation behavior of Ferro tungsten powder and mild steel slabs in the south neutron beam end of KAMINI Reactor. The results reveal that epithermal neutron attenuation in Ferro tungsten is better than in mild steel from plots of attenuation versus areal density and attenuation versus areal atom density. Fast neutron attenuation in Ferro tungsten is comparable to mild steel from plot of attenuation versus areal density. Ferro tungsten however shows higher fast neutron attenuation in plot of attenuation versus areal atom density. It can be deduced that, Ferro tungsten would be a better neutron attenuator compared to steel if its bulk density is increased. Ferro tungsten would therefore not only be an effective shield material than steel but a better substitute for steel in high temperature applications. (C) 2012 Elsevier Ltd. All rights reserved.