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 keeps, the necessity for secure and trustworthy how you can put off radioactive waste turns into ever extra serious. the final word objective for designing a predisposal waste-management approach depends upon generating waste packing containers compatible for garage, transportation and everlasting disposal. Cement-Based fabrics for Nuclear-Waste garage provides a roadmap for using cementation as an utilized method for the therapy of low- and intermediate-level radioactive wastes. assurance comprises, yet isn't really constrained to, a comparability of cementation with different solidification strategies, benefits of calcium-silicate cements over different fabrics and a dialogue of the long term suitability and safeguard of waste applications in addition to cement barriers.

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4 Conclusion The obtained experimental data allowed to make preliminary technological recommendations on production of cement compounds that satisfy the national waste acceptance requirements. The next step will be creation of full-scale pilot cementation facility and its testing using simulated pulp and real MCC pulp. 2 R&D on Cementation of Pulp with Complex Physical and Chemical. . Fig. 6 Cementation pilot facility with pulse mixer 19 Chapter 3 Cementation in High Energy Mixer of ILW Surrogate Slurry.

The porosity accessible to the water is homogeneous over the entire container and of the order of 50 %. The resistance to compression on the test specimens 11 Â 22 cm at 90 days is between 20 and 25 MPa. They are clearly greater than the 8 MPa required by ANDRA. The appearance of the mix is homogeneous. Some flaws (porosities 1 cm in size) were observed on the edges of the container. At microscopic level, small clusters of slurry are distributed homogeneously throughout the container. The cement matrix incorporates these slurry clusters (Fig.

The composition of the OPC studied after 1 year refers to composition at the left side of Fig. 5, while ESDRED and LAC after 1 year of hydration time will be around 25 and 28 % replacement level, respectively, as only a part of the silica fume and the slag had reacted. With more time, as the silica fume and also the unhydrated slag continue to react slowly, the mixtures studied will move more towards the right side of Fig. 5. 4000 LAC 3500 Ettringite 30% PC counts / - 3000 2500 C-S-H E E ESDRED E C calcite portlandite E 60% PC 2000 E 1500 OPC hydrotalcite portlandite ferrite 1000 portlandite 500 belite 0 5 10 15 20 2-theta / ° 25 30 35 Fig.

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