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AbstractAbstract
[en] Graphite casting scrap, fuel elements and nongraphite combustibles are calcined to impure oxides. These materials along with zircaloy fuel elements and refractory solids are leach-dissolved separately in HF-HNO3 acid to solubilize the contained enriched uranium. The resulting slurry is filtered and the clear filtrate (to which mineral acid solutions bearing enriched uranium may be added) are passed through solvent extraction. The solvent extraction product is filtered, precipitated with H2O2 and the precipitate calcined to U3O8. Metal is made from U3O8 by conversion to UO2, hydrofluorination and reduction to metal. Throughput is 150 to 900 kg uranium per year depending on the type of scrap
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Source
1984; 56 p; Plutonium/uranium recovery operations conference; Oak Ridge, TN (USA); 16-18 Oct 1984; CONF-8410166--4; Available from NTIS, PC A04/MF A01; 1 as DE85005965
Record Type
Report
Literature Type
Conference
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