Physicochemical properties of Cs borosilicate glasses containing CaO
Source abstract
Abstract
A series of Cs-borosilicate glasses of general formula (mol%): 17.5Na2O–2.5Cs2O–45SiO2–(35-x)B2O3–xCaO, where x varies from 0 to 10, were prepared by conventional melt quenching technique. Physicochemical properties like glass transition temperature, extent of volatilization loss of Cs and chemical durability of these glasses have been investigated in detail. Based on the Tg values obtained from DSC studies, it is confirmed that the glass network remains unaffected with increase in CaO content in the glass at the expense of B2O3. Cs loss as function of duration of heating revealed that the Cs evaporation follows diffusion controlled mechanism and the extent of loss increases with the increase of CaO incorporation in glass. Chemical durability of the glasses has been found to improve significantly with in the increase of CaO content in glass and this has been attributed to the formation of Ca and Si rich layer at the outer surface of the glass, as inferred from SEM with EDX analysis.
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Research context
OpenAlex topics: Glass properties and applications · Nuclear materials and radiation effects · Luminescence Properties of Advanced Materials
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References (25)
Show source-provided references
1. W. Lutze, Radioactive waste forms for the future, in: W. Lutze, R.C. Ewing (Eds.), North-Holland, Amsterdam, 1988, pp. 1–161 (Chapter 1).
2. Jahagirdar · Waste Manage. · 1998 · 18 · 26510.1016/S0956-053X(98)00025-7 ↗
3. L.A. Chick, B.F. Pieple, G.B. Mellinger, R.P. May, W.J. Gray, C.Q. Buckwalter, The effects of composition on properties in an 11 component nuclear waste glass system, US DOE Report No. PNL-3188, Pacific Northwest Laboratory, WA, USA, 1981.10.2172/6270428 ↗
4. Israd · J. Non Cryst. Solids · 1969 · 1 · 23510.1016/0022-3093(69)90003-9 ↗
5. Day · J. Non Cryst. Solids · 1976 · 21 · 34310.1016/0022-3093(76)90026-0 ↗
6. Trotignon · J. Nucl. Mater. · 1992 · 190 · 22810.1016/0022-3115(92)90088-3 ↗
7. Levitsk · Glass Ceram. · 2004 · 61 · 7310.1023/B:GLAC.0000034050.94462.78 ↗
8. Angeli · Phys. Chem. Glasses · 2001 · 42 · 279
9. R.C. Rastogi, J.D. Sehgal, K. Chandra, K.T. Thomas, Investigation of materials and methods for the fixation of low and medium level radioactive waste in stable solid media, BARC Report No. BARC-400, Bhabha Atomic Research Centre, India, 1969.
10. Stewart · 1985
11. Banerjee · J. Am. Ceram. Soc. · 2010 · 93 · 325210.1111/j.1551-2916.2010.03909.x ↗
12. Rana · Phys. Chem. Glasses · 1961 · 2 · 179
13. Dunken · J. Non Cryst. Solids · 1987 · 92 · 6110.1016/S0022-3093(87)80359-9 ↗
14. Israd · Phys. Chem. Glasses · 1986 · 27 · 55
15. Smets · J. Non Cryst. Solids · 1984 · 65 · 31910.1016/0022-3093(84)90056-5 ↗
16. Clark · J. Am. Ceram. Soc. · 1976 · 59 · 6210.1111/j.1151-2916.1976.tb09391.x ↗
17. Ledieu · J. Non Cryst. Solids · 2004 · 343 · 310.1016/j.jnoncrysol.2004.06.006 ↗
18. J.W. Mellor, A comprehensive treatise on inorganic and theoretical chemistry, vol. II, Longmans, Green and Co, London, New York, Toronto, 1948, pp. 813.
19. M.H. Langowski, J.G. Darab, P.A. Smith, Volatility literature of chlorine, iodine, cesium, strontium, technetium and rhenium; technetium and rhenium volatility testing, US DOE Report No. PNNL-11052, Pacific Northwest National Laboratory, USA, 1996.10.2172/211388 ↗
20. A.E. Greenberg, R.R. Trussell, L.S. Clesceri, M.A.H. Franson, Standard methods for the examination of water and waste water, 16th edition, American Public Health Association, Washington, DC, 1985.
21. ASTM standard test methods for determining chemical durability: Product consistency tests (PCT), ASTM-C-1285-94.
22. L.F. Oldfield, R.D. Wright, Advances in glass Technology, Pt-1, Technical papers of the VI International congress on glass, Washington, Dc, USA, Ed. The Am. Ceram. Soc., 1962.
23. G. Rudolph, J. Saidl, S. Drobnik, W. Guber, W. Hild, H. Krause, W. Muller, Lab scale R and D work on fission product solidification by vitrification and thermite process, in: Proceedings of Symposium on Manage of Radioactive Waste from Fuel Reprocessing, Jointly Edited by OECD Nuclear Energy Agency and IAEA, Paris, 1972, pp. 655–79.
24. Hench · Nucl. Chem. Waste Manage. · 1984 · 5 · 14910.1016/0191-815X(84)90045-7 ↗
25. Paul · J. Mater. Sci. · 1977 · 12 · 224610.1007/BF00552247 ↗