- Manufacture of Uranium from Phosphate Ores and Wet Phosphoric Acid
-
is present in apatites, because the ionic radius of uranium(Ⅳ) is cornparable to that of the calcium ion. In the wet process the apatite is digested with dilute sulfuric acid producing wet process phosphoric acid. Raw phosphoric acid produced by the wet process contains, depending upon the ore used, between 50 and 200 ppm U3O8. The uranium can be recovered from wet process acid by extraction. The extraction agents used are preferably a mixture of trioctylphosphine oxide (TOPO) and di-(2-ethylhexyl)-phosphate (DEHPA) in kerosene (process developed by the Oak Ridge National Laboratory) or a mixture of mono- and dioctylphenylesters of phosphoric acid. Further developments of the Oak Ridge National Laboratory process are the reduction stripping and oxidation stripping processes.
In the reduction stripping process uranium(Ⅳ) in the raw wet process acid is oxidized to uranium(Ⅵ) by treatment with sodium chlorate, hydrogen peroxide or air at 60 to 70°C, the uranium(Ⅵ) formed being extracted with trioctylphosphine oxide/di-(2-ethylhexyl)phosphate in kerosene and the resulting solution finally reductively stripped repeatedly with aqueous iron(Ⅱ) solutions. This results in an enrichment by a factor of 40. After oxidation of the stripped solution with sodium chlorate or ambient oxygen and renewed extraction of the uranium(Ⅵ) formed with trioctylphosphine oxide/di-(2-ethylhexyl)phosphate, the phosphoric acid is removed from the organic phase by washing. The uranium(Ⅵ) is then stripped with ammonium carbonate and precipitated as the ammonium diuranyl-tricarbonato-complex. This is filtered off, washed and calcined.
In the oxidation stripping process the uranium(Ⅵ) in the raw wet process acid is initially reduced to uranium(Ⅳ), which is extracted with a mixture of mono and dioctylphenyl esters of phosphoric acid in kerosene. Oxidation with sodium chlorate in phosphoric acid transfers the uranium to the aqueous phase and it is then extracted with trioctylphosphine oxide/di-(2-ethylhexyl)-phosphate, as in the reduction stripping process.
Prev:No record
Next:No record - 【Back】【Close 】【Print】【Add to favorite 】
- Related information
- Further Processing of Uranium and Plutonium Solutions
- Reprocessing of Spent Fuel Elements
- Reconversion of Uranium(Ⅵ) Fluoride into Uranium(Ⅳ) Oxide
- Conversion of Uranium Concentrates to Uranium Hexafluoride
- Manufacture of Uranium from Seawater
- Manufacture of Marketable Uranium Compounds ("Yellow Cake")
- Manufacture of Uranium from Uranium Ores
-
Health and Chemical more >
-
Hot Products
- 119478-55-6 Danofloxacin mesylate
- 512-04-9 Spirost-5-en-3-ol,(3b,25R)-
- 58213-06-2 Polyoxy(methyl-1,2-ethanediyl), .alpha.,.alpha.,.alpha.-1,2,3-propanetriyltris.omega.-(sulfooxy)-, triammonium salt
- 109-55-7 3-Dimethylaminopropylamine
- 71902-01-7 Sorbitan, isooctadecanoate
- 61788-97-4 Resin epoxy
- 14334-40-8 Pramiverine
- 25655-41-8 Povidone iodine
- 7693-46-1 4-Nitrophenyl chloroformate
- 1689-82-3 Phenol,4-(2-phenyldiazenyl)-
- 886360-86-7 Methyl 5-amino-2-(4-benzylpiperazin-1-yl)benzoate
- 68475-94-5 DIMER ACID DIGLYCIDYL ESTER