<p>This investigation presents important properties of Gd<sup>3+</sup> doped B<sub>2</sub>O<sub>3</sub>/SiO<sub>2</sub>/TeO<sub>2</sub>/Bi<sub>2</sub>O<sub>3</sub>/ZnO/BaO glass system coded as BiTeGd-x (x = 0, 1, 2, 3 &amp; 4&#xa0;mol%) synthesized by melt-quench method. On increasing the concentration of Gd<sub>2</sub>O<sub>3</sub> from 0 to 4&#xa0;mol%, we found the density enhancement from 5.323 to 5.579&#xa0;gcm<sup>− 3</sup>. From the FTIR analysis, the TeO<sub>4</sub>/TeO<sub>3</sub> ratio was found to be highest for BiTeGd-4 indicating greater number of TeO<sub>4</sub> units in the network. Vickers micro-indentation test showed continuous increase in microhardness (H) with Gd content with BiTeGd-4 having maximum H. The CIE chromaticity diagram corresponding to 470&#xa0;nm emission for BiTeGd-2 glass produced (x, y) = (0.285,0.306) which is nearer to pure white light coordinate. The radiation shielding parameters such as linear attenuation coefficient (LAC), effective atomic number (Z<sub>eff</sub>), tenth value layer (TVL) and mean free path (MFP) were determined from Photon Shielding and Dosimetry (PSD) software in 0.015–15&#xa0;MeV range. Maximum LAC and Z<sub>eff</sub>, as well as minimum TVL and MFP for BiTeGd-4 glass in the entire 0.015–15&#xa0;MeV energy range confirmed the potentiality BiTeGd-4 glass for gamma shielding application. The simulated results of LAC were also compared with the experimental results from NaI(Tl) detector for <sup>133</sup>Ba, <sup>137</sup>Cs and <sup>60</sup>Co radio-isotopes. The results suggested good agreement between the theoretical and experimental values. At photon energies <InlineEquation ID="IEq1"> <EquationSource Format="TEX">\(&lt;\)</EquationSource> <EquationSource Format="MATHML"><math> <mo>&lt;</mo> </math></EquationSource> </InlineEquation> 1.5&#xa0;MeV, the analysis of photon build-up factor showed lowest build-up for glass containing highest equivalent atomic number i.e. BiTeGd-4, which is also a quality of a good shielding material. BiTeGd-4 generated a highest (0.10624&#xa0;cm<sup>− 1</sup>) theoretical value of fast neutron removal cross-section.</p>

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Gd2O3 boro-tellurite glasses: structural, optical, thermal, mechanical and radiation blocking studies

  • Ashwitha Nancy D’Souza,
  • Sathi Sharma,
  • M. S. Murari,
  • M. I. Sayyed,
  • Sudha D. Kamath

摘要

This investigation presents important properties of Gd3+ doped B2O3/SiO2/TeO2/Bi2O3/ZnO/BaO glass system coded as BiTeGd-x (x = 0, 1, 2, 3 & 4 mol%) synthesized by melt-quench method. On increasing the concentration of Gd2O3 from 0 to 4 mol%, we found the density enhancement from 5.323 to 5.579 gcm− 3. From the FTIR analysis, the TeO4/TeO3 ratio was found to be highest for BiTeGd-4 indicating greater number of TeO4 units in the network. Vickers micro-indentation test showed continuous increase in microhardness (H) with Gd content with BiTeGd-4 having maximum H. The CIE chromaticity diagram corresponding to 470 nm emission for BiTeGd-2 glass produced (x, y) = (0.285,0.306) which is nearer to pure white light coordinate. The radiation shielding parameters such as linear attenuation coefficient (LAC), effective atomic number (Zeff), tenth value layer (TVL) and mean free path (MFP) were determined from Photon Shielding and Dosimetry (PSD) software in 0.015–15 MeV range. Maximum LAC and Zeff, as well as minimum TVL and MFP for BiTeGd-4 glass in the entire 0.015–15 MeV energy range confirmed the potentiality BiTeGd-4 glass for gamma shielding application. The simulated results of LAC were also compared with the experimental results from NaI(Tl) detector for 133Ba, 137Cs and 60Co radio-isotopes. The results suggested good agreement between the theoretical and experimental values. At photon energies \(<\) < 1.5 MeV, the analysis of photon build-up factor showed lowest build-up for glass containing highest equivalent atomic number i.e. BiTeGd-4, which is also a quality of a good shielding material. BiTeGd-4 generated a highest (0.10624 cm− 1) theoretical value of fast neutron removal cross-section.