GB893320A - Purification of uranium ore concentrates - Google Patents
Purification of uranium ore concentratesInfo
- Publication number
- GB893320A GB893320A GB3233960A GB3233960A GB893320A GB 893320 A GB893320 A GB 893320A GB 3233960 A GB3233960 A GB 3233960A GB 3233960 A GB3233960 A GB 3233960A GB 893320 A GB893320 A GB 893320A
- Authority
- GB
- United Kingdom
- Prior art keywords
- uranium
- nitric acid
- concentrate
- hexafluoride
- minimum value
- 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
- 229910052770 Uranium Inorganic materials 0.000 title abstract 11
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 title abstract 11
- 239000012141 concentrate Substances 0.000 title abstract 6
- 238000000746 purification Methods 0.000 title 1
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 abstract 5
- 229910017604 nitric acid Inorganic materials 0.000 abstract 5
- CDBYLPFSWZWCQE-UHFFFAOYSA-L Sodium Carbonate Chemical compound [Na+].[Na+].[O-]C([O-])=O CDBYLPFSWZWCQE-UHFFFAOYSA-L 0.000 abstract 3
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 abstract 3
- QGZKDVFQNNGYKY-UHFFFAOYSA-N Ammonia Chemical compound N QGZKDVFQNNGYKY-UHFFFAOYSA-N 0.000 abstract 2
- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 abstract 2
- 239000012535 impurity Substances 0.000 abstract 2
- 238000002386 leaching Methods 0.000 abstract 2
- QGZKDVFQNNGYKY-UHFFFAOYSA-O Ammonium Chemical compound [NH4+] QGZKDVFQNNGYKY-UHFFFAOYSA-O 0.000 abstract 1
- VHUUQVKOLVNVRT-UHFFFAOYSA-N Ammonium hydroxide Chemical compound [NH4+].[OH-] VHUUQVKOLVNVRT-UHFFFAOYSA-N 0.000 abstract 1
- BVKZGUZCCUSVTD-UHFFFAOYSA-L Carbonate Chemical compound [O-]C([O-])=O BVKZGUZCCUSVTD-UHFFFAOYSA-L 0.000 abstract 1
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 abstract 1
- ZOKXTWBITQBERF-UHFFFAOYSA-N Molybdenum Chemical compound [Mo] ZOKXTWBITQBERF-UHFFFAOYSA-N 0.000 abstract 1
- QAOWNCQODCNURD-UHFFFAOYSA-N Sulfuric acid Chemical compound OS(O)(=O)=O QAOWNCQODCNURD-UHFFFAOYSA-N 0.000 abstract 1
- 229910021529 ammonia Inorganic materials 0.000 abstract 1
- 239000000908 ammonium hydroxide Substances 0.000 abstract 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 abstract 1
- 239000001569 carbon dioxide Substances 0.000 abstract 1
- 229910002092 carbon dioxide Inorganic materials 0.000 abstract 1
- 239000000706 filtrate Substances 0.000 abstract 1
- 238000003682 fluorination reaction Methods 0.000 abstract 1
- 238000004519 manufacturing process Methods 0.000 abstract 1
- 229910052750 molybdenum Inorganic materials 0.000 abstract 1
- 239000011733 molybdenum Substances 0.000 abstract 1
- 238000006386 neutralization reaction Methods 0.000 abstract 1
- 229910052760 oxygen Inorganic materials 0.000 abstract 1
- 239000001301 oxygen Substances 0.000 abstract 1
- 230000001706 oxygenating effect Effects 0.000 abstract 1
- 230000001376 precipitating effect Effects 0.000 abstract 1
- 238000000926 separation method Methods 0.000 abstract 1
- 239000002002 slurry Substances 0.000 abstract 1
- 229910052708 sodium Inorganic materials 0.000 abstract 1
- 239000011734 sodium Substances 0.000 abstract 1
- 229910000029 sodium carbonate Inorganic materials 0.000 abstract 1
- 239000001117 sulphuric acid Substances 0.000 abstract 1
- 235000011149 sulphuric acid Nutrition 0.000 abstract 1
- SANRKQGLYCLAFE-UHFFFAOYSA-H uranium hexafluoride Chemical compound F[U](F)(F)(F)(F)F SANRKQGLYCLAFE-UHFFFAOYSA-H 0.000 abstract 1
- 229910052720 vanadium Inorganic materials 0.000 abstract 1
- LEONUFNNVUYDNQ-UHFFFAOYSA-N vanadium atom Chemical compound [V] LEONUFNNVUYDNQ-UHFFFAOYSA-N 0.000 abstract 1
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
- C22B60/0239—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors nitric acid containing 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
-
- 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
-
- 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)
- Life Sciences & Earth Sciences (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Engineering & Computer Science (AREA)
- Organic Chemistry (AREA)
- Geology (AREA)
- Environmental & Geological Engineering (AREA)
- Manufacturing & Machinery (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Inorganic Chemistry (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
Uranium ore concentrates which have been obtained by soda leaching of uranium ores are freed from vanadium and molybdenum impurities by treating the concentrate with aqueous nitric acid which selectively dissolves the uranium. On addition of nitric acid to such a concentrate, the pH initially falls to a minimum value after which it rises and finally falls again; the nitric acid addition should be such that the slurry has a pH between the above-mentioned initial minimum value and 0,5 thereabove. Uranium passes into solution whilst the impurities remain in the undissolved residue. The uranium-containing solution after separation from the residue may be treated with ammonium hydroxide to precipitate the uranium as ammonium uranate, this step preferably being effected at 25 DEG -70 DEG C. and at a final filtrate pH of 6-13. The initial concentrate may be obtained by leaching the uranium ore with sodium carbonate at 100 DEG C. under two atmospheres pressure of oxygen and precipitating the uranium as insoluble sodium uranate by adding sodium hydroxide to a pH of 11 or above; alternatively the carbonate solution may be neutralized with sulphuric acid, boiled to remove carbon dioxide and the uranium precipitated by neutralization with ammonia. The nitric acid attack on such concentrate is preferably effected at temperatures of 70-105 DEG C. with nitric acid of 5-36% strength. The purified uranium values finally obtained are particularly suitable for the production of uranium hexafluoride by gaseous reduction to the dioxide followed by hydrofluorination to the tetrafluoride and fluorination to the desired hexafluoride.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US893320XA | 1960-02-10 | 1960-02-10 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB893320A true GB893320A (en) | 1962-04-04 |
Family
ID=22217080
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB3233960A Expired GB893320A (en) | 1960-02-10 | 1960-09-20 | Purification of uranium ore concentrates |
Country Status (1)
| Country | Link |
|---|---|
| GB (1) | GB893320A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0599509A1 (en) * | 1992-11-16 | 1994-06-01 | Westinghouse Electric Corporation | Uranium carbonate extraction process |
| CN104870370A (en) * | 2012-11-16 | 2015-08-26 | 霍尼韦尔国际公司 | Separation and recovery of molybdenum values from uranium process distillate |
-
1960
- 1960-09-20 GB GB3233960A patent/GB893320A/en not_active Expired
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0599509A1 (en) * | 1992-11-16 | 1994-06-01 | Westinghouse Electric Corporation | Uranium carbonate extraction process |
| CN104870370A (en) * | 2012-11-16 | 2015-08-26 | 霍尼韦尔国际公司 | Separation and recovery of molybdenum values from uranium process distillate |
| US9567237B2 (en) | 2012-11-16 | 2017-02-14 | Honeywell International Inc. | Separation and recovery of molybdenum values from uranium process distillate |
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