Development of Al2O3-Bi2O3-B2O3 Glasses for Neutron Shielding Material

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Abstract:

A glass system with chemical formula xB2O3:20Bi2O3:(100-x) Al2O3 (x = 55, 60, 65, 70, 75 and 80 mol%) is prepared by melt quenching technique and were investigated the physical and neutron shielding properties. The physical properties were investigated by density, molar volume and discussed with different Al2O3 contents. The neutron shielding property was investigated by Monte Carlo techniques (FLUKA and GEANT4 codes) and neutron equivalent dose rate measurements. As a result, neutron shielding capacity of glass samples decrease with increased Al2O3 content, so increased B2O3 content is a result of positive effects on neutron shielding.

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Key Engineering Materials (Volumes 675-676)

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430-433

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January 2016

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© 2016 Trans Tech Publications Ltd. All Rights Reserved

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[1] K.J. Singh, N. Singh, R.S. Kaundal, K. Singh, Gamma-ray shielding and structural properties of PbO-SiO2 glasses, Journal of Nuclear Instruments and Methods in Physics Research B. 266 (2008) 944-948.

DOI: 10.1016/j.nimb.2008.02.004

Google Scholar

[2] J. Kaewkhao, A. Pokaipisit, P, Limsuwan, Study on borate glass system containing with Bi2O3 and BaO for gamma-ray shielding materials: Comparison with PbO, Journal of Nuclear Materials. 399 (2010) 38-40.

DOI: 10.1016/j.jnucmat.2009.12.020

Google Scholar

[3] B. Tellili, Y. Elmahroug, C, Souga, Calculation of fast neutron removal cross sections for different lunar soils, Journal of Advances in Space Research. 53 (2014) 348-352.

DOI: 10.1016/j.asr.2013.10.023

Google Scholar