Abstract
Five series of modified glasses based on a reference borosilicate formulation (GP 98) have been prepared and investigated. On the basis of comparisons of properties of the different glasses, two compositions have been selected for more detailed investigations and for technical application in the future. Simultaneously, glass products with real HAW oxides from German fuel reprocessing have been investigated. No structural change caused by irradiation has been detected after two year storage.
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References
W. Guber, W. Hild, F. Kaufmann, H. Koschorke, H. Krause, G. Rudolph, J. Saidl and K. Scheffler, Labscale and Pilot Plant Experiments on the Solidification of High-level Wastes at Karlsruhe Nuclear Research Centre, “Proceedings of the Symposium on the Management of Radioactive Wastes from Nuclear Fuel Cycle,” pp. 271–280, Vienna (March 1976).
W. Guber, L. Kahn and J. Saidl, “Recent Experiments on Fixation of High Activity Wastes in Karlsruhe,” KfK 2179 (1975).
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© 1979 Plenum Press, New York
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Guber, W., Hussain, M., Kahl, L., Ondracek, G., Saidl, J. (1979). Preparation and Characterization of an Improved High Level Radioactive Waste (HAW) Borosilicate Glass. In: McCarthy, G.J., et al. Scientific Basis for Nuclear Waste Management. Springer, Boston, MA. https://doi.org/10.1007/978-1-4615-9107-8_4
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DOI: https://doi.org/10.1007/978-1-4615-9107-8_4
Publisher Name: Springer, Boston, MA
Print ISBN: 978-1-4615-9109-2
Online ISBN: 978-1-4615-9107-8
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