Abstract
This investigation reports the experimental results of neutron transport and shielding properties of heavy concretes made from locally available ilmenite and magnetite sand. The experiment has been carried out with a 252Cf source and a BF 3 detector as a long counter. The thickness dependent removal cross section has been investigated and found to vary from 0.0936 cm −1 at 5 cm to 0.0346 cm −1 at 100 cm and 0.0990 cm −1 at 5 cm to 0.0366 cm −1 at 100 cm for ilmenite and magnetite concretes respectively. The results illustrate the effectiveness of ilmenite and magnetite heavy concretes so far as their sheilding properties are concerned. These materials may be used as a neutron shield in reactors, accelerators and neutron sources.
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