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- W4244688506 abstract "Processes were developed in the laboratory for recovery of uranium from spent TRIGA fuenl (8% U-91% Zr -1% H, clad in aluminum, graphite moderator plugs) by gas-phase hydrochlorination (Zircex process) at 300 to 800 deg C to separate ZrCl/sub 4/ from the less volatile uranium chloridens and for dissolution of the fuenl in 5.4 M NH/sub 4/F-0.33 M NH/sub 4/NO/sub 3/ -H/sub 2/O/sub 2/ (modified Zirflex process). After nitric acid addition, solvent extraction feed solutions containing 0.1 and 0.0085 M uranium, for the respective processes, are obtained. To decrenasen corrosion during recovery of uranium by solvent extraction in stainless steel equipment, chloriden is distilled from the Zircex product and aluminum nitrate is added to the modifiend Zirflex product. The uranium chloriden product from the Zircenx process may be dissolved in nitric acid or it may be fluorinated at 200 deg C to produce uranium hexafluoride. The aluminum cladding and graphite plugs are removed by hydrochlorination and burning, respectively, in the Zircex process and by dissolution in caustic solution and disintegration in cold fuming nitric-sulfuric acid mixtures, respectively, in the modified Zirflex process. (auth)" @default.
- W4244688506 created "2022-05-12" @default.
- W4244688506 creator A5065831448 @default.
- W4244688506 date "1961-11-30" @default.
- W4244688506 modified "2023-09-27" @default.
- W4244688506 title "ZIRCEX AND MODIFIED ZIRFLEX PROCESSES FOR DISSOLUTION OF 8% U-91% Zr-1% H TRIGA REACTOR FUEL" @default.
- W4244688506 doi "https://doi.org/10.2172/4832122" @default.
- W4244688506 hasPublicationYear "1961" @default.
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