The present work deals with the shielding properties of lead glass composites to find out its integrity for
practical shielding applications and radiological safety. Composites of different lead oxide ratios (x = 0, 5,
10, 15 and 25 wt.%) have been prepared by the Nasser Glass and Crystal Company (Egypt). Attenuation
measurements have been carried out using a collimated emitted beam from a fission 252Cf (100 lg)
neutron source, and the neutron–gamma spectrometer with stilbene scintillator. The pulse shape discriminating
(P.S.D.) technique based on the zero cross-over method was used to discriminate between
neutron and gamma-ray pulses. Thermal neutron fluxes were measured using the BF3 detector and thermal
neutron detection system. The attenuation relations were used to evaluate fast neutron macroscopic
effective removal cross-section RR-Meas (cm1), gamma rays total attenuation coefficient l (cm1) and
thermal neutron macroscopic cross-section RMeas (cm1). Theoretical calculations have been achieved
using MCNP5 code to calculate the same two parameters. Also, MERCSF-N program was used to calculate
fast neutron macroscopic removal cross-section RR-MER (cm1). Measured and MCNP5 calculated results
have been compared and were found to be in reasonable agreement.