Effect of Ce-dopant on photon interaction parameters of zirconolite-based borosilicate glass ceramics
Source abstract
Abstract
In the present investigation, 70 wt% of zirconolite (CaZr 1-xCe xTi 2O 7, x = 0, 0.2, 0.4, 0.6, 0.8 and 1) and 30 wt% of sodium borosilicate glass (NaB 0.5Al 0.5Si 2O 6) (sample C0 to C10) have been synthesized. The photon interaction parameters viz. mass attenuation coefficient, effective atomic number, effective electron density, mean free path, and half value layer have been investigated for glass-ceramic samples at incident photon energies of 59.58 keV, 81.2 keV, 356 keV, 662 keV, 1173 keV and 1333 keV. Furthermore, effective neutron removal cross-section values, mass stopping power (MSP) and range of alpha particles and proton, were also calculated using SRIM codes. Moreover, gamma-ray energy absorption buildup factor (EABF) and exposure buildup factor (EBF) were also estimated. The experimental results are in agreement with the theoretically calculated values using WinXCOM program. Among the given prepared samples, C10 shows the best shielding properties, and C0 shows the best capability for neutron absorption. The MSP and projected range of α-particles and protons in all the prepared samples show very small variation with the change of Ce content in zirconolite in the energy range upto 15 MeV. The measured values are extensively desirable in fission and fusion reactors, medical applications, shielding researchers, and radiation physics.
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Research context
OpenAlex topics: Radiation Shielding Materials Analysis · Nuclear materials and radiation effects · Advanced X-ray and CT Imaging
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (36)
Show source-provided references
1. Materials science of high-level nuclear waste immobilization10.1557/mrs2009.12 ↗
2. Immobilisation of high-level nuclear reactor wastes in SYNROC10.1038/278219a0 ↗
3. Radiation effects in crystalline ceramics for the immobilization of high-level nuclear waste and plutonium10.1557/JMR.1998.0205 ↗
4. Ceramic waste forms for actinides10.2113/gselements.2.6.365 ↗
5. Reduction and structural modification of zirconolite on He+ ion irradiation10.1016/j.nimb.2016.04.020 ↗
6. Solid solution limits in SYNROC zirconolite10.1016/0191-815X(83)90019-0 ↗
7. Solid solution of metal oxides in the zirconolite phase CaZrTi2O7. II: the ternary phase CaZrxTi3−xO710.1016/0022-4596(92)90287-6 ↗
8. Waste loading capability of zirconolite- A review10.1063/5.0052493 ↗
9. Alpha-recoil damage in natural zirconolite and perovskite10.2343/geochemj.15.229 ↗
10. Alpha-recoil damage in natural zirconolite (CaZrTi2O7)10.1016/0022-3115(83)90058-2 ↗
11. Intrinsic luminescence of un-doped borate glasses10.1016/j.jlumin.2017.03.071 ↗
12. Improvement of BaO:B2O3: Fly ash glasses: radiation shielding, physical and optical properties10.1016/j.anucene.2012.05.017 ↗
13. Structure of glass
14. Heavy metal oxide glasses as gamma rays shielding material10.1016/j.nucengdes.2016.07.029 ↗
15. Comparative study of gamma-ray shielding and some properties of PbO-SiO2-Al2O3 and Bi2O3-SiO2-Al2O3 glass systems10.1016/j.radphyschem.2013.09.015 ↗
16. Nuclear radiation shielding using barium borosilicate glass ceramics10.1016/j.jpcs.2020.109437 ↗
17. Investigation of the physical properties and gamma-ray shielding capability of borate glasses containing PbO, Al2O3 and Na2O10.1007/s00339-019-3020-z ↗
18. Alpha-recoil damage in zirconolite (CaZrTi2O7)10.1557/JMR.1986.0564 ↗
19. Probing swift heavy ion irradiation damage in Nd-doped zirconolite10.1016/j.nimb.2019.06.002 ↗
20. The impact of PbF2 on the ionizing radiation shielding competence and mechanical properties of TeO2-PbF2 glasses and glass-ceramics10.1016/j.ceramint.2020.09.100 ↗
21. Determination of structural features of different Perovskite ceramics and investigation of ionizing radiation shielding properties10.1007/s10854-021-06603-0 ↗
22. Radiation shielding performance of Co2O3-TeO2-Li2O-ZrO2 glass-ceramics10.1007/s41779-022-00774-7 ↗
23. Environment friendly La3+ ions doped phosphate glasses/glass-ceramics for gamma radiation shielding: their potential in nuclear safety applications10.1016/j.ceramint.2020.07.256 ↗
24. Synthesis, characterization, and performance assessment of new composite ceramics towards radiation shielding applications10.1016/j.jallcom.2021.163173 ↗
25. Phase analysis and reduction behavior of Ce dopant in zirconolite10.1007/s10967-019-06536-3 ↗
26. Gerward · Rad. Phys. Chem. · 2001 · 60 · 2310.1016/S0969-806X(00)00324-8 ↗
27. X-ray attenuation coefficients of elements and mixtures10.1016/0370-1573(81)90014-4 ↗
28. Determination of shielding parameters for different types of resins10.1016/j.anucene.2013.09.007 ↗
29. Assessment of nuclear shielding and alpha/proton mass stopping power properties of various metallic glasses10.1007/s00339-019-3105-8 ↗
30. Calculations of stopping power, and range of ions radiation (alpha particles) interaction with different materials and human body parts
31. F. Ziegler, SRIM – the stopping and range of ions in matter, http://www.srim.org, 2008 (accessed 16 February 2020).
32. An Approximation of Gamma-Ray Buildup Factors by Modified Geometrical Progression10.13182/NSE83-A18222 ↗
33. Angular width of a narrow beam for X-Ray linear attenuation coefficient measurements10.1016/j.radphyschem.2006.01.008 ↗
34. Energy absorption and exposure buildup factors for some polymers and tissue substitute materials: photon energy, penetration depth and chemical composition dependence10.1088/0952-4746/31/1/008 ↗
35. Determination of energy absorption and exposure buildup factors by using G-P fitting approximation for radioprotective agents10.1080/09553002.2016.1175681 ↗
36. Evaluation of three different glassy composites (quinary matrix designed using Cr2O3/Na2O/MnO2) in respect of radiation shielding behaviors10.1080/10420150.2021.1986822 ↗