GB845842A - Improvements in and relating to uranium extraction processes - Google Patents

Improvements in and relating to uranium extraction processes

Info

Publication number
GB845842A
GB845842A GB40349/58A GB4034958A GB845842A GB 845842 A GB845842 A GB 845842A GB 40349/58 A GB40349/58 A GB 40349/58A GB 4034958 A GB4034958 A GB 4034958A GB 845842 A GB845842 A GB 845842A
Authority
GB
United Kingdom
Prior art keywords
uranium
solution
eluant
nitrate
ozone
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired
Application number
GB40349/58A
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Publication of GB845842A publication Critical patent/GB845842A/en
Expired legal-status Critical Current

Links

Classifications

    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01GCOMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00Compounds of uranium

Abstract

In the extraction of uranium values from liquors obtained by leaching uranium ores with aqueous alkali-metal carbonate solutions, the liquor is ozonised and filtered to obtain a solution which, after any necessary adjustment, has a pH of 9.5-11.5, a carbonate concentration calculated as Na2CO3 of less than 30 g.p.l., a bicarbonate concentration calculated as NaHCO3 of less than 15 g.p.l., and a sulphate concentration calculated as SO4 of less than 6 g.p.l., and this solution is contacted with an anion exchange resin. The barren solution may be recycled to the ore leaching step. The uranium adsorbed as a tetravalent uranyl carbonate is recovered by elution, for example, with sodium nitrate or chloride. The eluate thus obtained may be acidified and a salt having the same anion as the eluant added to precipitate insoluble salts. For example, a calcium salt may be added, such as calcium nitrate when sodium nitrate is the eluant. The acid employed for the acidification may also have the same anion as the eluant. The precipitated salts may be removed by filtration, the uranium salts in the resulting solution extracted by an immiscible solvent, for example, a mixture of paraffin and tributyl phosphate, and the remaining aqueous solution neutralised by the addition of a substance having the same cation as the eluant, for example sodium hydroxide. The resulting solution may be employed to elute further quantities of uranium from the anionexchange material. The uranium values may be extracted from the organic solvent as araryl nitrate or chloride for example, by means of water. A suitable rate of ozone supply in the initial ozonising step is from 1 to 6 grams of ozone per hour for a rate of solution supply of 40 litres per hour. The ozonisation is preferably carried out at room temperature for a period of 10-15 minutes, and the ozone is conveniently introduced by means of a microporous diffuser formed of fritted silica or carborundum, or of agglomerated carbon. The filtration after ozonisation is normally carried out in the presence of powdered filtering aids, such as diatomaceous earth, asbestos, or silica.
GB40349/58A 1957-12-17 1958-12-15 Improvements in and relating to uranium extraction processes Expired GB845842A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR845842X 1957-12-17

Publications (1)

Publication Number Publication Date
GB845842A true GB845842A (en) 1960-08-24

Family

ID=9313046

Family Applications (1)

Application Number Title Priority Date Filing Date
GB40349/58A Expired GB845842A (en) 1957-12-17 1958-12-15 Improvements in and relating to uranium extraction processes

Country Status (1)

Country Link
GB (1) GB845842A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4606894A (en) * 1980-09-26 1986-08-19 Ecodyne Corporation Uranium recovery from carbonate leach liquors using carboxylic acid cation exchange resin
CN111547773A (en) * 2020-04-24 2020-08-18 核工业北京化工冶金研究院 Preparation of U from uranium-containing sodium carbonate solution3O8Method (2)
CN113406180A (en) * 2021-06-07 2021-09-17 核工业北京地质研究院 Method for confirming favorable temperature range of enriched uranium with pH value change
CN117551894A (en) * 2023-10-31 2024-02-13 湖南中核金原新材料有限责任公司 Method for improving uranium leaching rate in extraction residues of tantalum-niobium ores

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4606894A (en) * 1980-09-26 1986-08-19 Ecodyne Corporation Uranium recovery from carbonate leach liquors using carboxylic acid cation exchange resin
CN111547773A (en) * 2020-04-24 2020-08-18 核工业北京化工冶金研究院 Preparation of U from uranium-containing sodium carbonate solution3O8Method (2)
CN111547773B (en) * 2020-04-24 2022-09-20 核工业北京化工冶金研究院 Preparation of U from uranium-containing sodium carbonate solution 3 O 8 Method (2)
CN113406180A (en) * 2021-06-07 2021-09-17 核工业北京地质研究院 Method for confirming favorable temperature range of enriched uranium with pH value change
CN117551894A (en) * 2023-10-31 2024-02-13 湖南中核金原新材料有限责任公司 Method for improving uranium leaching rate in extraction residues of tantalum-niobium ores
CN117551894B (en) * 2023-10-31 2024-04-09 湖南中核金原新材料有限责任公司 Method for improving uranium leaching rate in extraction residues of tantalum-niobium ores

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