|
Author(s) |
Praveena, N.; Jena, H.; Bera, S.; Ravi Kumar; Jha, S. N.; Bhattacharyya, D. (BARCF-K;A&MPD)
|
Source |
Progress in Nuclear Energy, 2021. Vol. 131: Article no. 103579 |
ABSTRACT
|
The modified sodium borosilicate glass was synthesized by incorporating CaO, TiO2 and Al2O3 to the primary glass forming constituents (SiO2, B2O3 and Na2O) and on melting the mixture at 1373 - 1473K/3h by melt quench method. Uranium loaded analogues were synthesized by adding varying amounts of UO3 (2,4,6 and 8 mol %) to the borosilicate glass forming reagents then on melting at 1373-1473K. The U-loaded matrices were characterized by XRD to ensure the formation of glass matrices. Solubility of uranium in sodium borosilicate glass has been investigated. Further, the glasses were characterized by X-ray photoelectron spectroscopy (XPS) to unravel the oxidation states of uranium in the modified glass composition. X-ray absorption spectroscopy (EXAFS) revealed the chemical environment of uranium in the glass matrix indicating the coordination number of U in glass. |
|
|
|