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Swelling capacity and permeability of an unprocessed and a processed bentonitic clay
Authors:DW Oscarson  DA Dixon and MN Gray
Institution:

aAtomic Energy of Canada Ltd., Whiteshell Nuclear Research Establishment, Pinawa, Man. R0E 1L0, Canada

Abstract:Research on the longevity of potential bentonite-based barrier materials is an important part of the Canadian Nuclear Fuel Waste Management Program. Valuable information on the longterm effectiveness of bentonitic barriers can be obtained by examining the properties of unprocessed bentonites from natural deposits. This study compares the swelling capacity (Ps) and hydraulic conductivity (K) of an unprocessed (clay that has not been ground and dried by the supplier) and a processed bentonite from south-central Saskatchewan, Canada. The clay deposit is 75 to 85 Ma old. At a given clay density, the processed bentonite exhibits a greater P3 and a lower K than the unprocessed clay. This can be at least partially attributed to the partial cementation of the unprocessed bentonite particles; this cementation is likely ruptured when the clay is ground during processing. Even though K for the unprocessed clay is higher than that of the processed clay, it is still low enough (< 1011m/s) to meet the permeability requirements of a barrier material in a nuclear fuel waste disposal vault. The unprocessed clay also has the has the ability to self seal: exposure to water, the normalized flow rate of water through some samples was as high as 10-5 m3/s, but the rate rapidly decreased to < 10-10m3/s the clay absorbed water and swelled. The data indicate that the unprocessed bentonite clay maintains anacceptably high swelling capacity and low permeability millions of years after deposition.
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