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The Interaction Between Nuclear Waste Glass and Ordinary P ortland Cement
Author(s) -
Ferrand Karine,
Liu Sanheng,
Lemmens Karel
Publication year - 2013
Publication title -
international journal of applied glass science
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.383
H-Index - 34
eISSN - 2041-1294
pISSN - 2041-1286
DOI - 10.1111/ijag.12047
Subject(s) - portland cement , materials science , radioactive waste , cement , waste management , nuclear engineering , metallurgy , engineering
The interaction between simulated reference waste glasses SON 68 and SM 539, and cement has been studied in suspensions of ordinary P ortland cement and synthetic cement water with p H 13.5 at 30°C. The cement appears to trigger glass dissolution by consumption of glass matrix components. This leads to fast glass dissolution at a constant rate with formation of a porous gel layer on the glass. A glass dissolution model has been proposed considering that the silicon coming from the glass reacts with portlandite to form C ‐ S ‐ H phases. The transformation of C ‐ S ‐ H into C ‐ A ‐ S ‐ H phases is a second parallel driving force especially for the A l‐rich SM 539 glass. After consumption of the portlandite, the glass alteration rate is expected to decrease.