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- W2001151913 abstract "Analytical programs have been described for uranium recovery processes for aluminum-uranium and zirconium-uranium reactor fuel elements. It is the purpose of this paper to describe the analytical program for the uranium recovery process involving stainless-steel-uranium-reactor fuel elements. The recovery process consists of a two-step dissolution and the regular liquid-liquid solvent extraction using TBP in kerosene. Sulfuric acid is used to dissolve the stainless steel. As a result of the sulfuric acid dissolution, the uranium is converted to a slurry. The uranium slurry is then dissolved in nitric acid. After the nitric acid dissolution, the feed material is compatible with the extraction columns used at the Idaho Chemical Processing Plant for other type fuel elements previously described. In order to analyze samples of dissolver solutions for constituents necessary for plant operation, three new analytical methods were developed. These methods are a rapid method for determining uranium, one for nitrate and one for sulfate. Methods are described for uranium, acidity, specific gravity, nitrate and sulphate in the dissolver solution, and for small amounts of uranium in the extraction column raffinates. Samples of dissolver solution and first cycle aqueous raffinate contain large amounts of fission products. These samples require shielded facilities for analytical work. The remote analytical facility described by Dykes and his co-workers was used for this work. Precision and accuracy data are given for the analytical methods described." @default.
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- W2001151913 date "1960-01-01" @default.
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- W2001151913 title "Analytical program for processing stainless steel-uranium dioxide reactor fuel elements" @default.
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- W2001151913 doi "https://doi.org/10.1016/0039-9140(60)80229-9" @default.
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