Studying the shielding properties of lead glass composites using neutrons and gamma rays. (April 2015)

• Record Type: Journal Article
• Authors: Osman, A.M.; El-Sarraf, M.A.; Abdel-Monem, A.M.; El-Sayed Abdo, A.
• Is Part Of: Annals of nuclear energy. Volume 78(2015:Apr.)
• Page Start: 146
• Page End: 151
• Publication Date: 2015-04
• Subjects: Lead glass composites -- Neutron removal cross-section -- Gamma attenuation coefficient -- MCNP5 code -- MERCSF-N program; Nuclear energy -- Periodicals; Nuclear engineering -- Periodicals; 621.4805
• DOI: 10.1016/j.anucene.2014.11.046
• Languages: English
• ISSNs: 0306-4549

Abstract

Highlights: Samples of sodalime silica glass loaded with different ratios of PbO were prepared. Leaded glass composites were investigated for radiation shielding. Experimental and theoretical attenuation parameters were studied. Experimental and theoretical (MCNP5) results were in good agreement. Abstract: 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 252 Cf (100 μg) 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 ΣR-Meas (cm −1 ), gamma rays total attenuation coefficient μ (cm −1 ) and thermal neutron macroscopic cross-section ΣMeas (cm −1 ). 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 ΣR-MER (cm −1 ). Measured and MCNP5 calculated results have been compared and were found to be in reasonable agreement.