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Title: Canadian refining practice in the production of uranium trioxide by solvent extraction with tributyl phosphate

Conference ·
OSTI ID:4281999

The recovery of high-purity uranium trioxide from uranium-bearing concentrates by solvent extraction with tributyl phosphate is described. Gravity and chemical concentrates, containing 10 to 80% U{sub 3}O{sub 8}, are blended and digested continuously with 55% nitric acid in cascade dissolvers to give a slurry containing about 300 g U/liter, 3N in free nitric acid. Uranium is extracted from the slurry in pulsed columns using 25 vol. % tributyl phosphate in an inert kerosene diluent. Extraction of thorium and other impurities is minimized by maintaining the uranium content at a high saturation density. Residual impurities and free nitric acid are removed from the solvent using a de-ionized water scrub. Uranium is re-extracted from the solvent with de-ionized water to give an aqueous solution containing 100 g U/liter. The stripped solvent is treated with aqueous sodium carbonate (7 wt. %) to remove residual uranium and any mono- or dibutyl- phosphate, and it is then stored for reuse. The uranyl-nitrate solution (100 g U/liter) is concentrated in two thermo-syphon evaporators and is then denitrated batch-wise in stainless steel kettles to give uranium trioxide. This is carried by a vacuum system to storage hoppers, pulverized, and packed in drums for shipment. Sulfuric acid is added to the aqueous raffinate from the initial extraction to convent combined nitric acid into free nitric acid, which is recovered by distillation in a forced-circulation evaporator. The nitric oxide gases from digestion and denitration are converted to dilute nitric acid (30%) in an absorption power. This dilute acid together with the acid recovered from the raffinate is concentrated to 55 to 60% nitric acid in a bubble-cap column. The bottoms from the raffinate evaporator are neutralized to a pH between 5 and 6 with hydrated-lime slurry to precipitate iron, arsenic, and other elements. The solid residue is separated on a rotating-drum filter and trucked to a disposal area. The filtrate, which satisfies the requirements of the International Commission for the Control of Boundary Waters for waste disposal, is pumped into Lake Ontario. (auth)

Research Organization:
Eldorado Mining and Refining Ltd., Port Hope, Ontario (Canada)
NSA Number:
NSA-13-007301
OSTI ID:
4281999
Report Number(s):
A/CONF.15/P/228; AECL-638
Resource Relation:
Conference: 2. United Nations International Conference on the Peaceful Uses of Atomic Energy, Geneva (Switzerland), Jun 1958
Country of Publication:
Canada
Language:
English