Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2016, Vol. 27 ›› Issue (4): 103 doi: 10.1007/s41365-016-0099-1


Gamma-ray and neutron shielding efficiency of Pb-free gadolinium-based glasses

V. P. Singh 1, N. M. Badiger 1, S. Kothan 2, S. Kaewjaeng 2, T. Korkut 3, H. J. Kim 4, J. Kaewkhao 5   

  1. 1 Department of Physics, Karnatak University, Dharwad 580003, India
    2 Department of Radiologic Technology, Faculty of Associated Medical Sciences, Chiang Mai University, Chiang Mai 50200, Thailand
    3 Department of Nuclear Energy Engineering, Faculty of Engineering, Sinop University, 57000 Sinop, Turkey
    4 Department of Physics, Kyungpook National University, Daegu 702-701, Korea
    5 Center of Excellence in Glass Technology and Materials Science, Nakhon Pathom Rajabhat University, Nakhon Pathom 73000, Thailand
  • Contact: V. P. Singh
PDF ShareIt Export Citation
V. P. Singh, N. M. Badiger, S. Kothan, S. Kaewjaeng, T. Korkut, H. J. Kim, J. Kaewkhao. Gamma-ray and neutron shielding efficiency of Pb-free gadolinium-based glasses.Nuclear Science and Techniques, 2016, 27(4): 103     doi: 10.1007/s41365-016-0099-1


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- 10SiO2-10CaO-xGd2O3 (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.