Affiliation:
1. Department of Chemistry, B.B. College, Asansol, West Bengal, India
Abstract
To safe environment from radioactive waste it is important to fix them as radioactive waste glasses. The corrosion behavior of radioactive waste glasses in water is significantly important. Radionuclides return to the biosphere by means of leaching from waste form into ground water. Finally the ground water containing the radionuclide are transported to the surface. In this study, the preparation, characterization and leaching behavior of some borosilicate (BS) and lead iron phosphate (LIP) of different chemical composition doped with simulated nuclear waste oxide were investigated. We measured the pH found to be in the range from 6.78 up to 7.79 of the leachate solution at normal temperature and at varying time intervals. Leaching study of these glasses were conducted with the help of Soxhlet distillation apparatus with distilled water upto 24 hours and for BS9 - BS12 upto 100 hours duration. Weight losses were are measured with respect to time of leaching. Leach rate of some borosilicate glass samples loaded with uranium are calculated from surface area measurements. The results are reported in the range 1.34x10-4 g.m-2.hr-1 and 6.26 x 10-4 g.m-2.hr-1 respectively at 90°C.
Funder
University Grants Commission
Publisher
Oriental Scientific Publishing Company
Subject
Pharmacology (medical),Complementary and alternative medicine,Pharmaceutical Science
Reference24 articles.
1. J. Mukerji and A. S. Sanyal ”Historical series: Indian work on vitreous matrices for the containment of radioactive waste 1960-1980”, Glass Technol., vol 45, no 3,pp 117-25, 2004
2. S. V. Raman, “The effect of mixed modifiers on nuclear waste glass processing, leaching and Raman spectra”, J. Mater. Res., Vol. 13, No. 1, Jan 1998
3. A. S. Pankou, O. G. Batyukhova, M. I. Ojoven and W. E. Lee, “Simulation of Self-Irradiation of High-sodium content Nuclear Waste Glasses”. Mater Res. Soc. Symp. Proc. Vol. 985, 2007.
4. Jain, V., & Pan, Y.M. (2000). High-Level waste glass dissolution in simulated internal waste package environments. Scientific research on the back-end of the fuel cycle for the 21 century, (p. 575). France
5. T. Yanagi, M. Yoshizoe and N. Nakatsuka, “Leach Rates of Lead-Iron Phosphate Glass Waste Forms”, Department of Nuclear Engineering, Faculty of Engineering, Osaka University WM’02 Conference, February, 24-28, 2002, Tucson, AZ1 16 .