GB774371A - Improvements in or relating to extraction of uranium from ore - Google Patents
Improvements in or relating to extraction of uranium from oreInfo
- Publication number
- GB774371A GB774371A GB2822451A GB2822451A GB774371A GB 774371 A GB774371 A GB 774371A GB 2822451 A GB2822451 A GB 2822451A GB 2822451 A GB2822451 A GB 2822451A GB 774371 A GB774371 A GB 774371A
- Authority
- GB
- United Kingdom
- Prior art keywords
- uranium
- solution
- sodium
- carbonate
- alkali metal
- 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
Links
Classifications
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
- C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
- C22B60/0252—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
- C22B60/0265—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries extraction by solid resins
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
- C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
- C22B60/0221—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching
- C22B60/0226—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors
- C22B60/0234—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors sulfurated ion as active agent
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
- C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
- C22B60/0221—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching
- C22B60/0247—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using basic solutions or liquors
Landscapes
- Engineering & Computer Science (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Chemical & Material Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Geology (AREA)
- Manufacturing & Machinery (AREA)
- Environmental & Geological Engineering (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Manufacture And Refinement Of Metals (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
Uranium is extracted from its ores by leaching with an aqueous alkali metal carbonate solution containing a dissolved persulphate salt whereby the uranium passes into solution and a uranium-containing concentrate is recovered therefrom, preferably by precipitation as a diurnate with an alkali metal hydroxide. Alternatively the uranium - containing solution may be contacted with an anion exchange resin to absorb the uranium which is then recovered by elution with an aqueous salt solution. The alkali metal carbonate employed for leaching is preferably sodium carbonate the solution suitably containing 5 to 20 per cent thereof. Sodium and ammonium per-sulphates are preferred oxidizing agents. According to an example an uranium ore was mixed with a solution containing 10 per cent by weight of sodium carbonate and 4 per cent of sodium persulphate and the resulting pulp was heated to 60 DEG C. with gentle agitation. The extract was treated with sodium hydroxide to precipitate the uranium as sodium diuranate. The filtrate was then evaporated and further sodium persulphate was added thereto and the solution treated with carbon dioxide to reduce the pH to 11.8 after which it was employed to treat further ore. Alternatively the uranium may be recovered from solution by an anion exchanger in which case the sodium carbonate and bicarbonate concentrations are preferably adjusted to less than <FORM:0774371/III/1> and <FORM:0774371/III/2> respectively. The anion exchanger may be in chloride sulphate or carbonate form and the absorbed uranium may be eluted with a solution of sodium chloride, bicarbonate or sulphate or ammonium carbonate or nitrate.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB2822451A GB774371A (en) | 1951-12-01 | 1951-12-01 | Improvements in or relating to extraction of uranium from ore |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB2822451A GB774371A (en) | 1951-12-01 | 1951-12-01 | Improvements in or relating to extraction of uranium from ore |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB774371A true GB774371A (en) | 1957-05-08 |
Family
ID=10272278
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB2822451A Expired GB774371A (en) | 1951-12-01 | 1951-12-01 | Improvements in or relating to extraction of uranium from ore |
Country Status (1)
| Country | Link |
|---|---|
| GB (1) | GB774371A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2416954A1 (en) * | 1978-02-08 | 1979-09-07 | Pechiney Ugine Kuhlmann | NON-POLLUTING TREATMENT OF URANIUM EFFLUENTS FROM AN ALKALINE ATTACK OF A URANIUM ORE CONTAINING SULFUR |
| FR2416955A1 (en) * | 1978-02-08 | 1979-09-07 | Pechiney Ugine Kuhlmann | NON-POLLUTING TREATMENT OF URANIFIC ALKALINE EFFLUENTS CONTAINING SO4 IONS = |
| US11384411B2 (en) * | 2017-06-02 | 2022-07-12 | Dow Global Technologies Llc | Recovery of uranium |
| CN115572848A (en) * | 2022-09-26 | 2023-01-06 | 核工业北京化工冶金研究院 | Process method capable of realizing efficient leaching and eluent regeneration of uranium-loaded resin |
-
1951
- 1951-12-01 GB GB2822451A patent/GB774371A/en not_active Expired
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2416954A1 (en) * | 1978-02-08 | 1979-09-07 | Pechiney Ugine Kuhlmann | NON-POLLUTING TREATMENT OF URANIUM EFFLUENTS FROM AN ALKALINE ATTACK OF A URANIUM ORE CONTAINING SULFUR |
| FR2416955A1 (en) * | 1978-02-08 | 1979-09-07 | Pechiney Ugine Kuhlmann | NON-POLLUTING TREATMENT OF URANIFIC ALKALINE EFFLUENTS CONTAINING SO4 IONS = |
| US11384411B2 (en) * | 2017-06-02 | 2022-07-12 | Dow Global Technologies Llc | Recovery of uranium |
| CN115572848A (en) * | 2022-09-26 | 2023-01-06 | 核工业北京化工冶金研究院 | Process method capable of realizing efficient leaching and eluent regeneration of uranium-loaded resin |
| CN115572848B (en) * | 2022-09-26 | 2023-12-15 | 核工业北京化工冶金研究院 | Technological method capable of realizing efficient leaching of uranium-bearing resin and regeneration of leaching agent |
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