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Radioactive high-level waste glass studies

Leaching of Fully Radioactive High-Level Waste Glass and Waste-Geologic Environment Interaction Studies... [Pg.75]

Studies of the immobilization behavior of Cd, Cr, and V in the cement matrices shown above revealed that (i) Cd is effectively retained in all cements and shows no sensitivity to the leachate pH and (ii) both NMLs of Cr and V are maximized at intermediate levels of alumina in the cement matrix and minimized at high and low alumina contents, presumably related to the amphoteric nature of Al (Heimann et al, 1992 Ivey et al, 1990). Multicomponent systems tests of the interaction of cement and radioactive waste forms (used UO2 fuel, fuel recycle waste glass) have provided evidence that actinides (plutonium 239 -1- 240, americium 241, curium 244) would be efficiently adsorbed onto cement (Heimann, 1988a), presumably related to the presence of apatite structures (Beall and Allard, 1982). [Pg.149]


See other pages where Radioactive high-level waste glass studies is mentioned: [Pg.323]    [Pg.161]    [Pg.54]    [Pg.585]    [Pg.135]    [Pg.383]    [Pg.347]    [Pg.181]    [Pg.102]    [Pg.103]    [Pg.107]    [Pg.666]   


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