This study focused on the radiation protection features of the Ag2O doped boro-tellurite glass samples in the form of (x)Ag2O/(100-x)(65B2O3-35TeO2) where x=10, 15, 20, 25 and 30 mol%. by using Phy-X / PSD software, the radiation protection parameters such as mass attenuation coefficient (MAC), linear attenuation coefficient (LAC), half-value layer (HVL), mean free path (MFP), total atomic and electronic cross-sections (ACS and ECS), effective atomic number (Zeff) , effective electron density (Neff) and effective conductivity (σeff) of present glasses were calculated in the photon energy range of 0.015-15 MeV. In order to evaluation the usability of these glasses in terms of radiation protection, the all investigated protection parameters were also calculated for commercial RS 253 glass and some concretes such as ordinary concrete (OC), hematite-serpenite (HS) and basalt-magnetite (BM) that are commonly used as shielding material in the nuclear application. The results obtained were evaluated in terms of both photon energy and chemical composition of the glasses examined. Additionally, the results obtained for the examined glasses were compared with the corresponding values obtained for the comparison materials presented to determine the best radiation protection glass. It was clearly observed that the MAC, LAC, ACS, ECS and Zeff values increased with the increasing of molar doping percentage Ag2O in the glasses. It was found that the radiation protection capacities of the Ag2O doped boro-tellurite glasses is found higher than the other compared materials. Maximum MAC, LAC, ACS, ECS and Zeff values were observed in the sample of G5 that contains 30% Ag2O. This study indicates that the disilver oxide doped tellurite glasses can be developed as radiation protection materials for many nuclear applications.
Mass attenuation coefficient radiation shielding tellurite glasses effective atomic number effective conductivity
This study focused on the
radiation protection features of the Ag2O doped boro-tellurite glass
samples in the form of (x)Ag2O/(100-x)(65B2O3-35TeO2)
where x=10, 15, 20, 25 and 30 mol%. by using Phy-X / PSD software, the
radiation protection parameters such as mass attenuation coefficient (MAC),
linear attenuation coefficient (LAC), half-value layer (HVL), mean free path (MFP),
total atomic and electronic cross-sections (ACS and ECS), effective atomic
number (Zeff) , effective
electron density (Neff)
and effective conductivity (σeff)
of present glasses were calculated in the photon energy range of 0.015-15 MeV. In
order to evaluation the usability of these glasses in terms of radiation
protection, the all investigated protection parameters were also calculated for
commercial RS 253 glass and some concretes such as ordinary concrete (OC),
hematite-serpenite (HS) and basalt-magnetite (BM) that are commonly used as
shielding material in the nuclear application. The results obtained were
evaluated in terms of both photon energy and chemical composition of the
glasses examined. Additionally, the results obtained for the examined glasses
were compared with the corresponding values obtained for the comparison
materials presented to determine the best radiation protection glass. It was
clearly observed that the MAC, LAC, ACS, ECS and Zeff values
increased with the increasing of molar doping percentage Ag2O in the
glasses. It was found that the radiation protection capacities of the Ag2O
doped boro-tellurite glasses is found higher than the other compared materials.
Maximum MAC, LAC, ACS, ECS and Zeff values
were observed in the sample of G5 that contains 30% Ag2O. This study
indicates that the disilver oxide doped tellurite glasses can be developed as
radiation protection materials for many nuclear applications.
Mass attenuation coefficient radiation shielding tellurite glasses effective atomic number effective conductivity
Primary Language | English |
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Subjects | Metrology, Applied and Industrial Physics |
Journal Section | Fizik / Physics |
Authors | |
Publication Date | March 1, 2020 |
Submission Date | October 30, 2019 |
Acceptance Date | November 28, 2019 |
Published in Issue | Year 2020 |