GB2198723A - Separating uranium from uranium bearing materials - Google Patents
Separating uranium from uranium bearing materials Download PDFInfo
- Publication number
- GB2198723A GB2198723A GB08728419A GB8728419A GB2198723A GB 2198723 A GB2198723 A GB 2198723A GB 08728419 A GB08728419 A GB 08728419A GB 8728419 A GB8728419 A GB 8728419A GB 2198723 A GB2198723 A GB 2198723A
- Authority
- GB
- United Kingdom
- Prior art keywords
- uranium
- process according
- slurry
- sulphur dioxide
- oxygen
- 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.)
- Withdrawn
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
- C22B60/0221—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
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G43/00—Compounds of uranium
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- Chemical & Material Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Organic Chemistry (AREA)
- Geology (AREA)
- Engineering & Computer Science (AREA)
- Environmental & Geological Engineering (AREA)
- Inorganic Chemistry (AREA)
- Manufacturing & Machinery (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Manufacture And Refinement Of Metals (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
Uranium is separated from uranium bearing materials by treating the material with a mineral acid to form a slurry and passing a mixture of sulphur dioxide and oxygen containing gas into the slurry. The uranium solution is then separated from the residual ore material. The mineral acid is suitably dilute sulphuric acid and the volume ratio of sulphur dioxide to oxygen is suitably in the range 1:2 to 1:20.
Description
PROCESS FOR SEPARATING URANIUM FROM URANIUM BEARING MATERIALS
The present invention relates to a process for the separation of uranium from uranium bearing materials.
Most uranium minerals are friable and in general are not effectively separated from the gangue or waste constituents by physical methods such as flotation. Uranium can be dissolved from its ores by mineral acids and if uranium is present in the ore in its lower valency reduced state, as is usual, an oxidising agent must also be used in the dissolution process. The most commonly used oxidising agents are manganese dioxide (pyrolusite), sodium chlorate, hydrogen peroxide and Caro's acid.
The present invention relates to a novel process for the separation of uranium from uranium bearing materials that has advantages over known processes under certain conditions.
Thus according to thapresent invention there is provided a process for the separation of uranium from uranium bearing materials comprising the steps of (a) treating the material with a mineral acid to form a slurry, (b) passing a mixture of sulphur dioxide and an oxygen containing gas into the slurry so as to convert the uranium into its higher oxidation state thereby rendering the uranium soluble, and (c) extracting the uranium by a conventional technique. The steps may be performed simultaneously or sequentially.
The mineral acid is suitably dilute sulphuric acid and the mixture of sulphur dioxide to oxygen is suitably in the volume ratio 1:2 to 1:20.
While not wishing to be bound by any theory, as iron containing minerals invariably occur with the uranium ore and sufficient amounts of this iron are soluble in the mineral acid, the function of the added oxidant is generally believed to be the oxidation of ferrous ion to ferric ion, the latter sometimes being referred to as the 'true' uranium oxidant (U4+ + 2Fe3+
U6+ + 2Fe2+).
The action of sulphur dioxide/oxygen containing gas mixtures in effecting this process is surprising as oxygen itself is not a sufficiently strong oxidant for this conversion and sulphur dioxide is well known as a reducing agent.
The invention will now be described by way of example only.
After mining, the uranium ore is crushed and ground and is then leached for several hours in a dilute acid solution through which a sulphur dioxide/oxygen mixture is bubbled. The volume ratio of sulphur dioxide:oxygen is 1:10. The temperature of the slurry may be ambient but elevated temperatures are preferred, e.g. 80 to 950C.
Following the dissolution of the uranium, the uranium bearing solution may be separated from the residual ore solids e.g. by filtration. The solution is then further purified by ion exchange or solvent extraction to obtain uranium of sufficient purity.
Alternatively the slurry may be treated directly e.g. by contact with suitable resins.
The sulphur dioxide and oxygen are suitably pre-mixed and emerge into the solution~by use of a sparge tube.
Claims (11)
1. A process for the separation of uranium from uranium bearing materials comprising the steps of (a) treating the material with a mineral acid to form a slurry, (b) passing a mixture of sulphur dioxide and an oxygen containing gas into the slurry so as to convert the uranium into its highest oxidation state thereby rendering the uranium soluble, and (c) extracting the uranium by a conventional technique.
2. A process according to claim 1 in which the steps are performed simultaneously.
3. A process according to claim 1 in which the steps are performed sequentially.
4. A process according to any of the preceding claims in which the volume ratio of sulphur dioxide to oxygen is in the range 1:2 to 1:20.
5. A process according to any of the preceding claims in which the volume ratio of sulphur dioxide to oxygen is 1:10.
6. A process according to any of the preceding claims in which the temperature of the slurry is above ambient temperature.
7. A process according to any of the preceding claims in which the temperature of the slurry is 800C and 950C.
8. A process according to any of the preceding claims in which the resultant uranium bearing solution is separated from the residual ore solids by filtration.
9. A process according to claim 8 in which the separated uranium bearing solution is further purified to obtain uranium by ion-exchange or solvent extraction.
A A process according to any of claims 1 to 7 in which the resultant uranium bearing solution with the residual ore solids is treated with ion exchange resins to recover uranium.
11. A process for separation of uranium from uranium bearing materials as hereinbefore described and with reference to the examples.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB868630316A GB8630316D0 (en) | 1986-12-18 | 1986-12-18 | Separation process |
Publications (2)
Publication Number | Publication Date |
---|---|
GB8728419D0 GB8728419D0 (en) | 1988-02-10 |
GB2198723A true GB2198723A (en) | 1988-06-22 |
Family
ID=10609249
Family Applications (2)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB868630316A Pending GB8630316D0 (en) | 1986-12-18 | 1986-12-18 | Separation process |
GB08728419A Withdrawn GB2198723A (en) | 1986-12-18 | 1987-12-04 | Separating uranium from uranium bearing materials |
Family Applications Before (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB868630316A Pending GB8630316D0 (en) | 1986-12-18 | 1986-12-18 | Separation process |
Country Status (1)
Country | Link |
---|---|
GB (2) | GB8630316D0 (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE3922866A1 (en) * | 1988-08-01 | 1990-02-08 | Draftex Ind Ltd | SEALING STRIP |
FR2716683A1 (en) * | 1994-02-25 | 1995-09-01 | Boc Gases Australia Ltd | Uranium extraction process. |
WO2011116426A1 (en) * | 2010-03-24 | 2011-09-29 | Bhp Billiton Olympic Dam Corporation Pty Ltd | Process for leaching refractory uraniferous minerals |
Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB760191A (en) * | 1953-10-20 | 1956-10-31 | Mini Of Mines And Technical Su | Sulphur dioxide leaching of uranium containing material |
EP0113649A1 (en) * | 1982-12-09 | 1984-07-18 | Boliden Aktiebolag | A method for working-up complex sulphidic ore concentrates |
-
1986
- 1986-12-18 GB GB868630316A patent/GB8630316D0/en active Pending
-
1987
- 1987-12-04 GB GB08728419A patent/GB2198723A/en not_active Withdrawn
Patent Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB760191A (en) * | 1953-10-20 | 1956-10-31 | Mini Of Mines And Technical Su | Sulphur dioxide leaching of uranium containing material |
EP0113649A1 (en) * | 1982-12-09 | 1984-07-18 | Boliden Aktiebolag | A method for working-up complex sulphidic ore concentrates |
Non-Patent Citations (1)
Title |
---|
WO 85/01300 * |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE3922866A1 (en) * | 1988-08-01 | 1990-02-08 | Draftex Ind Ltd | SEALING STRIP |
DE3922866C2 (en) * | 1988-08-01 | 2001-11-22 | Gencorp Property Inc | Sealing strips |
FR2716683A1 (en) * | 1994-02-25 | 1995-09-01 | Boc Gases Australia Ltd | Uranium extraction process. |
WO2011116426A1 (en) * | 2010-03-24 | 2011-09-29 | Bhp Billiton Olympic Dam Corporation Pty Ltd | Process for leaching refractory uraniferous minerals |
Also Published As
Publication number | Publication date |
---|---|
GB8728419D0 (en) | 1988-02-10 |
GB8630316D0 (en) | 1987-01-28 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
WAP | Application withdrawn, taken to be withdrawn or refused ** after publication under section 16(1) |