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    Development of Al2O3-Bi2O3-B2o3 glasses for neutron shielding material
    (Trans Tech Publications Ltd, 2016) Tuscharoen, S.; Insiripong, S.; Korkut, T.; Kaewkhao, J.
    A glass system with chemical formula xB2O3:20Bi2O3:(100-x) Al2O3 (x = 55, 60, 65, 70, 75 and 80 mol%) was 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. © 2016 Trans Tech Publications, Switzerland.
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    Gamma-ray and neutron shielding efficiency of Pb-free gadolinium-based glasses
    (Springer Singapore Pte Ltd, 2016) Singh, V. P.; Badiger, N. M.; Kothan, S.; Kaewjaeng, S.; Korkut, T.; Kim, H. J.; Kaewkhao, J.
    The radiation shielding efficiency of material depends upon photon attenuation, exposure buildup factors and neutron removal capacity. A newly developed Pb-free gadolinium-based glasses in compositions (80-x) B2O3-10SiO(2)-10CaO-xGd(2)O(3) (where x = 15, 20, 25, 30 and 35 mol%) had completely been investigated for their shielding efficiency with Geant4 simulation for mass attenuation coefficients and neutron total macroscopic cross section and by calculating exposure buildup factors. The exposure buildup factors for photon energy from 0.015 to 15 MeV had been calculated up to 40 mean free paths using five factors geometric progression method. The mass attenuation coefficients of the Pb-free glasses were simulated for energies from 223 to 2614 keV and compared with the possible available experimental results. The neutron shielding efficiency of these glasses was discussed by calculating neutron total macroscopic cross section for energies from 1 eV to 14.1 MeV. Present investigations are found to be very useful for applications in nuclear engineering.