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Properties of radioactive wastes and waste containers. Quarterly progress report, October--December 1976. [Urea-formaldehyde; polymer; portland cement] [electronic resource].

Published
Upton, N.Y. : Brookhaven National Laboratory, 1977.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
Pages: 104 : digital, PDF file
Additional Creators
Brookhaven National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
The cumulative quantities of free standing water resulting from the solidification of simulated wastes with urea-formaldehyde (UF) and portland type II cement were determined. The effect of the waste/solidification agent ratio on the cumulative free standing water for selected wastes solidified with UF was found to be related to sample shrinkage. Urea-formaldehyde decontamination factors for free standing water were determined with /sup 137/Cs, /sup 85/Sr, /sup 60/Co, and /sup 59/Fe. With the exception of /sup 85/Sr for which UF was shown to have a decontamination factor of 1.6-1.9, the specific activity of the free standing water was essentially equal to that of the waste prior to solidification. The release of cesium from UF in distilled water was measured by a static leaching technique. The effect of the leachant renewal interval and the ratio of the leachant volume (V/sub L/) to the sample external geometric surface area (S) was examined. The proposed leachant renewal interval of once/day and V/sub L/S = 10cm was found to be satisfactory for leaching of these samples. Samples of a proprietary polymer agent developed by the Dow Chemical Company were tested to determine water loss with exposure to ambient air, weight loss with temperature (TGA), thermal conductivity, compressive strength and impact strength. Property measurements were made for water/binder volume ratios of from 1.0 to 2.0. No deterioration was observed for a portland type II cement sample with a water/cement ratio of 0.5 by weight subjected to fifty freeze-thaw cycles.
Report Numbers
E 1.99:bnl-nureg-50664
bnl-nureg-50664
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
04/01/1977.
"bnl-nureg-50664"
Colombo, P.; Neilson, R.M. Jr.
Funding Information
EY-76-C-02-0016
View MARC record | catkey: 13803926