By Z. Drace, M. I. Ojovan (auth.), Florence Bart, Céline Cau-di-Coumes, Fabien Frizon, Sylvie Lorente (eds.)
As the re-emergence of nuclear energy as a suitable strength resource on a world foundation keeps, the necessity for secure and trustworthy how one can eliminate radioactive waste turns into ever extra severe. the last word objective for designing a predisposal waste-management process is dependent upon generating waste bins compatible for garage, transportation and everlasting disposal. Cement-Based fabrics for Nuclear-Waste garage provides a roadmap for using cementation as an utilized approach for the therapy of low- and intermediate-level radioactive wastes. insurance contains, yet isn't constrained to, a comparability of cementation with different solidification ideas, benefits of calcium-silicate cements over different fabrics and a dialogue of the long term suitability and protection of waste applications in addition to cement barriers.
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5 hours 20 0 10 20 30 40 0 50 60 70 80 90 100 110 120 130 140 temps en heures Fig. 6 Semi-adiabatic calorimetry of the mix Fig. 7 Scanning electron microscopy—appearance of the freshly fractured matrix (1: slurry cluster; 2: hydrated matrix) The results of the characterizations performed in the laboratory comply with those obtained during determination of the cement formulation at laboratory scale. The production of this drum makes it possible to comprehend the increase in temperature due to the volume effect.
P. Glasser Department of Chemistry, University of Aberdeen, Meston Walk, Old Aberdeen AB24 3FX, UK F. Bart et al. A. Gisby et al. modelling the near-field processes, which govern the performance of proposed deep geological disposal repositories for nuclear waste. Early work [1–5] sought to develop pragmatic models with which to simulate the thermodynamic evolution of cements in the repository environment. In achieving this goal, of critical importance was the development of a robust description of the incongruent dissolution of C-S-H gel because of its major contribution to the longevity of the chemical barrier.
Submitted). While the nanosilica had reacted within the first days, the slag dissolved relatively slowly. However, after 1 year 90 % of the slag had reacted and the SEM/BSE pictures of the hydrated samples showed only the presence of a few unhydrated slag particles. A relatively dense microstructure was visible with only little coarse porosity. The pore solution after a hydration time of 1 year was dominated by sodium, potassium, hydroxide, as well as by the different sulfur species. The high fraction of sulfide indicates reducing conditions.
Cement-Based Materials for Nuclear Waste Storage by Z. Drace, M. I. Ojovan (auth.), Florence Bart, Céline Cau-di-Coumes, Fabien Frizon, Sylvie Lorente (eds.)