Abstract
The alteration of cement materials in a fractured repository was investigated by experimental and modelling techniques to predict the long-term evolution of a cementitious repository for the safety assessment of radioactive waste disposal. A flow-through experiment with an artificially fractured cement column sample was carried out, and the evolution of a chemical composition in discharged water and the distribution of mineral components in a solid matrix, which was dominated by the dissolution of portlandite and calcium-silicate hydrate (C-S-H), were observed. A coupling transport and chemical equilibrium calculation code, which includes a thermodynamic incongruent dissolution model of C-S-H, was developed to predict the alteration of the fractured cement materials. The advection transport of a component in a solution within a crack and the diffusion of a component in a solid matrix were modelled in the calculations. With the proposed model, the possible alteration of cement materials along a crack was described.
Original language | English |
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Pages (from-to) | 1257-1264 |
Number of pages | 8 |
Journal | Cement and Concrete Research |
Volume | 37 |
Issue number | 8 |
DOIs | |
Publication status | Published - 2007 Aug |
Externally published | Yes |
Keywords
- Calcium silicate hydrate (C-S-H)
- Calculation code
- Crack
- Leaching
- Radioactive waste
ASJC Scopus subject areas
- Building and Construction
- Materials Science(all)