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Download Cement-Based Materials for Nuclear Waste Storage by Z. Drace, M. I. Ojovan (auth.), Florence Bart, Céline PDF

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 an appropriate power resource on a global foundation maintains, the necessity for secure and trustworthy how you can get rid of radioactive waste turns into ever extra severe. the final word objective for designing a predisposal waste-management method 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 process for the remedy of low- and intermediate-level radioactive wastes. assurance comprises, yet isn't really constrained to, a comparability of cementation with different solidification strategies, merits of calcium-silicate cements over different fabrics and a dialogue of the long term suitability and security of waste applications in addition to cement barriers.

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This is achieved using data assessment tools within MTDATA, which allow parameters to be optimised to give the best possible agreement between calculated thermodynamic properties (such as heat capacities, activities, enthalpies of mixing), phase equilibria (solubilities) and collated experimental properties. The aim of the work described here has been to develop a flexible, yet rigorous model and associated thermodynamic data for the C-S-H system, at room and elevated temperatures, which are compatible with existing NPL oxide and aqueous species databases.

1 Measured pH values in the pore solution of OPC, LAC, and ESDRED pastes 4 Hydration of Blended Cements 37 Ettringite 360 days 4000 3500 56 days Hemicarbonate Portlandite 1-7 days C-S-H E E E E 7 days 3000 counts / - Hemicarbonate 1-56 days Monocarbonate E 2500 1 day 2000 1h 1500 unhydrated Gypsum ferrite 1000 C3A 500 Anhydrite 0 5 10 15 20 25 Alite 30 Alite/ belite 35 2-theta / ° Fig. 2 XRD of the hydration of ESDRED (60 % PC, 40 % silica fume, alkali-free accelerator). 1. 5 (Fig. 1), somewhat lower alkali concentrations than in an OPC system, but a relatively high Ca concentration of 30 mM.

The formation of these hydrates could be a cause of the increase in the viscosity of the mixture. As the viscosity increases, the retention of the material in 28 G. Cardinal et al. 80 47; 79,11 temperature in °C 70 60 50 44; 48,32 bottom center bottom outside bottom Intermediary top center top outside top Intermediary middle center middle outside middle Intermediary Placement of the thermocouples in the container. 40 30 20 0 20 40 60 80 100 time in hours 120 140 160 Fig. 5 Diagram showing the evolution of the temperatures in the container during setting the mixer increases, respectively, from 30 kg at the first concrete mix up to 60 kg after the last concrete mix.

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