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Many countries use cementitious materials (concrete, mortar, etc.) as a containment matrix for immobilization, as well as for engineered structures of disposal facilities Permeable formulations allow gas readily to escape, while impermeable barriers retard radionuclide transport and reduce access of ground water to the waste. Radionuclide release is dependent on the physicochemical properties of the waste forms and packages, and on environmental conditions.
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The main scope of this article is therefore to evaluate the applicability of bentonite as a concrete admixture, by means of the determination of basic physical and mechanical properties of several concrete mixtures. On the other hand, cement and concrete may be used to form backfills, ranging in permeability For this reason, basic physical properties and mechanical parameters of concretes containing different amount of bentonite were determined.
(2014) noticed that the dry density of concrete increased by 17% comparing with control mix with an increasing of the proportion of eafs as fine and coarse aggregate.
This book reports research findings on several interesting topics in waste disposal including geophysical methods in site studies, municipal solid waste disposal site investigation, integrated study of contamination flow path at a waste disposal site, nuclear waste disposal, case studies of disposal of municipal wastes in different environments. The broad research topics presented in this special issue emphasized the importance of cement and concrete technologies to solve the ongoing issues of radioactive waste management, including f1nps decommissioning and environmental recovery from radionuclide contamination.
