Processes for Recovery of Uranium and Thorium from Graphite-base Fuel Elements
Author: L. M. Ferris
Publisher:
Published: 1961
Total Pages: 42
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Author: L. M. Ferris
Publisher:
Published: 1961
Total Pages: 42
ISBN-13:
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Publisher:
Published: 1961
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DOWNLOAD EBOOKLaboratory-scale tests on methods for recovering uranium and thorium from graphite-base reactor fuel elements are reported. The 90% HNO/sub 3/ process, which involves simultaneous disintegration and leaching in 21 M HNO/sub 3/, is applicable to all fuel elenments which do not contain coated fuel particles. Leaching of irradiated (0.001% burnup) fuels containing 3 and 12% uranlum recovered approximates 99.3 and 99.9%, respectively, of the uranium in two 4-hr leaches with boiling acid. The graphite residue retained> 50% of the long-lived fission products. Three successive leaches of fuel containing uranium and thorium recovered approximates 99% of both elements. Uranium recoveries by combustion in oxygen followed by dissolution of the ash hn nitric acid or fluorlde-catalyzed nitric acid are quantitative only when the fuel is not coated, does not contain Al/sub 2/O/sub 3/-coated fuel particles, and is free from impurities such as iron. During combustion up to 95% of the Ru-106 was volatilized from irradiated specimens. Recoveries, by leaching with 70% HNO/sub 3/, from fuel specimens containing Al/sub 2/O/sub 3/-coated fuel particles were greater than 99% when the specimens were ground finer than 200 mesh to ensure crushing of the fuel particles. (auth).
Author: M. J. Bradley
Publisher:
Published: 1960
Total Pages: 44
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DOWNLOAD EBOOKAuthor: J. L. Cook
Publisher:
Published: 1964
Total Pages: 34
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Published: 1966
Total Pages: 44
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DOWNLOAD EBOOKAuthor: Raymond Eugene Blanco
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Published: 1962
Total Pages: 40
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DOWNLOAD EBOOKAuthor: Gareth John Morgan
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Published: 1970
Total Pages: 14
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DOWNLOAD EBOOKAuthor: F. W. Dodge
Publisher:
Published: 1960
Total Pages: 30
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Published: 1964
Total Pages: 12
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DOWNLOAD EBOOKAuthor:
Publisher:
Published: 1964
Total Pages: 212
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