Studies on the <br>Processing of Organic Liquid Wastes of the Type Organic Solvents and Liquid Scintillation Mixtures Generated at the Cernavodă Nuclear-Electric Station <br>

Studies on the
Processing of Organic Liquid Wastes of the Type Organic Solvents and Liquid Scintillation Mixtures Generated at the Cernavodă Nuclear-Electric Station

Abstract:

Organic liquid wastes (organic solvents solutions and liquid scintillation cocktails) were counted in a Model 2100 TR Packard TRI-CARB liquid scintillation analyzer. It was evaluated the performance of three commercially available liquid scintillation cocktails designed to measure tritium in organic samples. The non biodegradable cocktails don’t exhibit higher efficiencies as well as the biodegradable cocktails. The Ultima Gold XR cocktail is suitable for tritium detection in the liquid scintillation cocktails waste generated by a CANDU nuclear power plant. The Ultima Gold F cocktail could be used for tritium measurement in the organic solvent solutions waste. The next step was conditioning of these two types of waste into a stable monolithic form, which minimizes the probability to release radionuclides in the environment during their intermediate storage, handling and final disposal. There were studied three conditioning matrix: Portland cement-waste-aluminum stearate, Portland cement-waste-lime, Portland cement-waste lime-sodium silicate. Compression strength of hardened samples and the rate of release of tritium from the waste formed as a result of interaction with water (tritium leachability) were verified. The results have shown that the two types of organic liquid waste can be conditioned into a cement Portland and aluminum stearate matrix. Keywords: organic liquid waste, liquid scintillation analyzer, conditioning, Portland cement, compressive strength, tritium leachability

Issue: 2005, Volume 56, Issue 11

Pages:

This article is published under the Creative Commons Attribution 4.0 International License

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