GB846861A - Process of recovering uranium - Google Patents
Process of recovering uraniumInfo
- Publication number
- GB846861A GB846861A GB3281845A GB3281845A GB846861A GB 846861 A GB846861 A GB 846861A GB 3281845 A GB3281845 A GB 3281845A GB 3281845 A GB3281845 A GB 3281845A GB 846861 A GB846861 A GB 846861A
- Authority
- GB
- United Kingdom
- Prior art keywords
- uranium
- solution
- tetrachloride
- calutron
- treated
- 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
- C01—INORGANIC CHEMISTRY
- C01B—NON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
- C01B15/00—Peroxides; Peroxyhydrates; Peroxyacids or salts thereof; Superoxides; Ozonides
- C01B15/04—Metal peroxides or peroxyhydrates thereof; Metal superoxides; Metal ozonides; Peroxyhydrates thereof
- C01B15/047—Metal peroxides or peroxyhydrates thereof; Metal superoxides; Metal ozonides; Peroxyhydrates thereof of heavy metals
- C01B15/0475—Metal peroxides or peroxyhydrates thereof; Metal superoxides; Metal ozonides; Peroxyhydrates thereof of heavy metals of actinides
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G43/00—Compounds of uranium
- C01G43/01—Oxides; Hydroxides
-
- 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
-
- 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
-
- 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
- C22B60/0278—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries by chemical methods
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
- Y02P10/00—Technologies related to metal processing
- Y02P10/20—Recycling
Landscapes
- Chemical & Material Sciences (AREA)
- Organic Chemistry (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Engineering & Computer Science (AREA)
- Geology (AREA)
- Environmental & Geological Engineering (AREA)
- Manufacturing & Machinery (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Inorganic Chemistry (AREA)
- Chemical Kinetics & Catalysis (AREA)
- General Chemical & Material Sciences (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
In the separation of isotopes of uranium by means of a calutron, such as is described in Specification 816,772, by vaporization of a charge of uranium tetrachloride, the uranium values are recovered from parts of the calutron by washing them with a solvent for uranium whereby metal impurities including iron are introduced into the wash solution; the pH of the solution is then adjusted to 1:3, the solution refrigerated to produce ice crystals therein and then treated with hydrogen peroxide thereby precipitating uranium peroxide. The uranium peroxide may be calcined to the trioxide and the latter reacted with carbon tetrachloride to produce uranium pentachloride which on calcining <PICT:0846861/III/1> gives uranium tetrachloride for recycling to the calutron, or alternatively the uranium trioxide may first be reduced by methane to the dioxide and thereafter reacted with calcium tetrachloride to give uranium tetrachloride direct. As shown in Fig. 3, a solution derived from washing or acid treating parts of the calutron to take up the uranium values and generally contaminated with copper, iron, chromium and nickel, is first treated with carbonate-free ammonium hydroxide solution or excess ammonia gas thereby precipitating ammonium diuranate and the hydroxides of iron and chromium away from the copper and nickel which remain in solution as amine complexes. The precipitate after washing is taken up in nitric acid and depending on its ferric ion content is, or is not, treated with a complexing agent such as lactic acid, acetic acid or a fluoride ion thereby inhibiting the catalytic decomposing effects of the ferric ion on hydrogen peroxide. If the ferric ion content is below 3% this is not necessary. In either case the solution is then treated with ammonium hydroxide to adjust the pH between 1 and 3 and the solution thereafter cooled below its freezing point to form minute ice crystals. Pre-cooled hydrogen peroxide is added in excess and the solution is refrigerated to a solid mass at temperature for example of -45 DEG C. It is then thawed to the incipient freezing p range namely -2 to -10 DEG C. whereupon the solution may be filtered and the precipitate of uranium peroxide washed with an aqueous solution containing ammonium nitrate and hydrogen peroxide.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US846861XA | 1944-11-30 | 1944-11-30 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB846861A true GB846861A (en) | 1960-08-31 |
Family
ID=22186584
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB3281845A Expired GB846861A (en) | 1944-11-30 | 1945-12-04 | Process of recovering uranium |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB846861A (en) |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0054014A1 (en) * | 1980-11-24 | 1982-06-16 | FMC Corporation | Method of removing phosphorus impurities from yellowcake |
CN103397184A (en) * | 2013-07-31 | 2013-11-20 | 南昌航空大学 | Method for separating uranium and iron from tertiary amine organic phase by back extraction |
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 |
CN116354314A (en) * | 2021-12-27 | 2023-06-30 | 核工业北京化工冶金研究院 | Method for improving nitric acid solubility of uranium peroxide product |
-
1945
- 1945-12-04 GB GB3281845A patent/GB846861A/en not_active Expired
Cited By (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0054014A1 (en) * | 1980-11-24 | 1982-06-16 | FMC Corporation | Method of removing phosphorus impurities from yellowcake |
CN103397184A (en) * | 2013-07-31 | 2013-11-20 | 南昌航空大学 | Method for separating uranium and iron from tertiary amine organic phase by back extraction |
CN103397184B (en) * | 2013-07-31 | 2014-12-03 | 南昌航空大学 | Method for separating uranium and iron from tertiary amine organic phase by back extraction |
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 |
CN113406180B (en) * | 2021-06-07 | 2022-12-20 | 核工业北京地质研究院 | Method for confirming favorable temperature range of enriched uranium with pH value change |
CN116354314A (en) * | 2021-12-27 | 2023-06-30 | 核工业北京化工冶金研究院 | Method for improving nitric acid solubility of uranium peroxide product |
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