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Detailed Inspection of γ-Ray, Fast and Thermal Neutrons Shielding Competence of Calcium Oxide or Strontium Oxide Comprising Bismuth Borate Glassesopen access

Authors
Lakshminarayana, GandhamElmahroug, YoussefKumar, AshokTekin, Huseyin OzanRekik, NajehDong, MenggeLee, Dong-EunYoon, JonghunPark, Taejoon
Issue Date
May-2021
Publisher
MDPI Open Access Publishing
Keywords
B2O3-Bi2O3-CaO glass; B2O3-Bi2O3-SrO glass; PENELOPE code; Phy-X/PSD software; Radiation protection efficiency; γ-and neutron radiation
Citation
Materials, v.14, no.9, pp 1 - 20
Pages
20
Indexed
SCIE
SCOPUS
Journal Title
Materials
Volume
14
Number
9
Start Page
1
End Page
20
URI
https://scholarworks.bwise.kr/erica/handle/2021.sw.erica/113926
DOI
10.3390/ma14092265
ISSN
1996-1944
1996-1944
Abstract
For both the B2O3-Bi2O3-CaO and B2O3-Bi2O3-SrO glass systems, γ-ray and neutron attenuation qualities were evaluated. Utilizing the Phy-X/PSD program, within the 0.015–15 MeV energy range, linear attenuation coefficients (µ) and mass attenuation coefficients (µ/ρ) were calculated, and the attained µ/ρ quantities match well with respective simulation results computed by MCNPX, Geant4, and Penelope codes. Instead of B2O3/CaO or B2O3/SrO, the Bi2O3 addition causes improved γ-ray shielding competence, i.e., rise in effective atomic number (Zeff) and a fall in half-value layer (HVL), tenth-value layer (TVL), and mean free path (MFP). Exposure buildup factors (EBFs) and energy absorption buildup factors (EABFs) were derived using a geometric progression (G–P) fit-ting approach at 1–40 mfp penetration depths (PDs), within the 0.015–15 MeV range. Computed radiation protection efficiency (RPE) values confirm their excellent capacity for lower energy photons shielding. Comparably greater density (7.59 g/cm3), larger µ, µ/ρ, Zeff, equivalent atomic number (Zeq), and RPE, with the lowest HVL, TVL, MFP, EBFs, and EABFs derived for 30B2O3-60Bi2O3-10SrO (mol%) glass suggest it as an excellent γ-ray attenuator. Additionally, 30B2O3-60Bi2O3-10SrO (mol%) glass holds a commensurably bigger macroscopic removal cross-section for fast neutrons (ΣR) (=0.1199 cm−1), obtained by applying Phy-X/PSD for fast neutrons shielding, owing to the pres-ence of larger wt% of ‘Bi’ (80.6813 wt%) and moderate ‘B’ (2.0869 wt%) elements in it. 70B2O3-5Bi2O3-25CaO (mol%) sample (B: 17.5887 wt%, Bi: 24.2855 wt%, Ca: 11.6436 wt%, and O: 46.4821 wt%) shows high potentiality for thermal or slow neutrons and intermediate energy neutrons capture or absorption due to comprised high wt% of ‘B’ element in it. © 2021 by the authors. Licensee MDPI, Basel, Switzerland.
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