The vitrified High-Level Radioactive Waste (HLW) disposal was simulated in this study using an International Simple Glass, a simplified version of the French R7T7 reference glass (ISG). Using coupon samples of ISG and powdered Ankerite, a test for nuclear waste form (MCC-1) was assembled for (3-90 days). Ultrapure water was used to set up the systems, which were kept at 90°C with an initial pH of 6.3. Mg-Si precipitation was seen as a chemical effect of Ankerite on the ISG coupon, however the hydrated layer on the ISG was clogged by Ankerite's dissolution products, lowering the ISG corrosion rate compared to the ISG reference system. When the data are presented as mass glass dissolved per unit area, the greater the sodium releases and the higher the corrosion rates, implying that sodium is indicative of the ISG at lower surface area to volume.
Author(s) DetailsAli Al Dabbas
Department of Engineering Geology and Geotechnics, Faculty of Civil Engineering, Budapest University of Technology and Economics BME, Hungary, M?egyetem rakpart 3, Budapest 1111, Hungary and Jordan Atomic Energy Commission JAEC, Shafa Badran, P.O. Box 70, Amman, Jordan.
Katalin Kopecskó
Department of Engineering Geology and Geotechnics, Faculty of Civil Engineering, Budapest University of Technology and Economics BME, Hungary, M?egyetem rakpart 3, Budapest 1111, Hungary.
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