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A closer look at the structure and gamma-ray shielding properties of newly designed boro -tellurite glasses reinforced by bismuth (III) oxide

  • Hammam Abdurabu Thabit*
  • , Abd Khamim Ismail*
  • , N. N. Yusof
  • , M. I. Sayyed
  • , K. G. Mahmoud
  • , I. Abdullahi
  • , S. Hashim
  • *Corresponding author for this work

Research output: Contribution to journalArticlepeer-review

28 Scopus citations

Abstract

This work presents the synthesis and preparation of a new glass system described by the equation of (70-x) B2O3–5TeO2 –20SrCO3–5ZnO –xBi2O3, x = 0, 1, 5, 10, and 15 mol. %, using the melt quenching technique at a melting temperature of 1100 °C. The photon-shielding characteristics mainly the linear attenuation coefficient (LAC) of the prepared glass samples were evaluated using Monte Carlo (MC) simulation N-particle transport code (MCNP-5) at gamma-ray energy extended from 59 keV to 1408 keV emitted by the radioisotopes Am-241, Ba-133, Cs-137, Co-60, Na-22, and Eu-152. Furthermore, we observed that the Bi2O3 content of the glasses had a significantly stronger impact on the LAC at 59 and 356 keV. The study of the lead equivalent thickness shows that the performance of fabricated glass sample with 15 mol.% of Bi2O3 is four times less than the performance of pure lead at low gamma photon energy while it is enhanced and became two times lower the perforce of pure lead at high energy. Therefore, the fabricated glasses special sample with 15 mol.% of Bi2O3 has good shielding properties in low, intermediate, and high energy intervals.

Original languageEnglish
Pages (from-to)1734-1741
Number of pages8
JournalNuclear Engineering and Technology
Volume55
Issue number5
DOIs
StatePublished - May 2023
Externally publishedYes

Bibliographical note

Publisher Copyright:
© 2023 Korean Nuclear Society

Keywords

  • Bismuth (III) 0xide
  • Boro-tellurite glass
  • Monte Carlo simulation
  • Radiation shielding

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

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