Characterization of SiO2–PbO–CdO–Ga2O3 glasses for comprehensive nuclear shielding performance: Alpha, proton, gamma, neutron radiation


Tekin H. O., Kavaz E., Papachristodoulou A., Kamislioglu M., Agar O., Guclu E. E. A., ...Daha Fazla

Ceramics International, cilt.45, ss.19206-19222, 2019 (SCI-Expanded) identifier identifier

  • Yayın Türü: Makale / Tam Makale
  • Cilt numarası: 45
  • Basım Tarihi: 2019
  • Doi Numarası: 10.1016/j.ceramint.2019.06.168
  • Dergi Adı: Ceramics International
  • Derginin Tarandığı İndeksler: Science Citation Index Expanded (SCI-EXPANDED), Scopus
  • Sayfa Sayıları: ss.19206-19222
  • Anahtar Kelimeler: Ga2O3, Shielding parameters, MCNPX code, Build-up factor, Effective atomic number, BORATE GLASSES, RAY
  • Atatürk Üniversitesi Adresli: Evet

Özet

The present study focuses on the results on survey of exposure buildup factor, photon and neutron shielding parameters for B, C and D series SiO2-PbO-CdO-Ga2O3 glasses utilizing MCNPX Monte Carlo code. In order to check out the accuracy of MCNPX results, the computational values of mass attenuation coefficients were confirmed with those of XCOM database in relatively photon energy region of 0.020-20 MeV. The relative deviation between MCNPX and XCOM values is below 10% except for 0B and 2B at 0.060 MeV and 0D and 1D at 0.122 MeV. The gamma ray buildup factors for the three extended glass systems were also determined in a wide energy range of 0.02-15 MeV for penetration depths up to 15 mfp. In addition, some related radiation attenuation parameters have been estimated and deduced that among the selected glasses, C-series sample has best photon shielding performance while being B series glasses the superior materials for neutron, alpha and proton shielding. The results showed that C series glass samples among SPCG glasses have clear advantage in weight decrease in terms of shielding the X- and gamma rays in relatively photon energy region of 0.020-20 MeV. It can be concluded that certain types of glasses which include this kind of mixture may be considered an alternative material for radiation shielding practices.