GB844283A - Improvements in methods of separating uranium and thorium from each other - Google Patents
Improvements in methods of separating uranium and thorium from each otherInfo
- Publication number
- GB844283A GB844283A GB2306/57A GB230657A GB844283A GB 844283 A GB844283 A GB 844283A GB 2306/57 A GB2306/57 A GB 2306/57A GB 230657 A GB230657 A GB 230657A GB 844283 A GB844283 A GB 844283A
- Authority
- GB
- United Kingdom
- Prior art keywords
- thorium
- sulphate
- solution
- uranium
- sodium
- 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
- C01F—COMPOUNDS OF THE METALS BERYLLIUM, MAGNESIUM, ALUMINIUM, CALCIUM, STRONTIUM, BARIUM, RADIUM, THORIUM, OR OF THE RARE-EARTH METALS
- C01F15/00—Compounds of thorium
Landscapes
- Chemical & Material Sciences (AREA)
- Organic Chemistry (AREA)
- Life Sciences & Earth Sciences (AREA)
- Geology (AREA)
- Inorganic Chemistry (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
- Compounds Of Alkaline-Earth Elements, Aluminum Or Rare-Earth Metals (AREA)
Abstract
Uranium and thorium values are separately recovered from a raw material containing them by dissolving the raw material in a slight excess of mineral acid, adding a soluble sulphate in amounts at least equal to the uranium and thorium present, warming the solution to a temperature between 25 and 60 DEG C. and neutralizing to a pH of 2.8 to 5.2 whereupon thorium is precipitated in the form of a basic sulphate leaving the uranium in solution. The precipitating sulphate is preferably that of sodium, ammonium or magnesium. Neutralization may be effected by means of sodium carbonate, ammonium carbonate, ammonia or soda. According to Examples (1) uranothorianite is attacked with nitric acid at 40% strength at 80 DEG C. and after dilution with water the resulting solution is treated with anhydrous sodium sulphate and warmed to 35 DEG C. Neutralization is effected with sodium carbonate solution to a pH of 3.3. The basic thorium sulphate precipitate is washed with sodium sulphate solution and may be redissolved in nitric acid and reprecipitated to decrease the uranium content thereof. The sulphate cake may be converted to thorium hydroxide by treatment with caustic soda at 80 DEG C. (2) Thorium is precipitated from an acid solution as in (1) above and the residual thorium in solution is finally precipitated by the addition of oxalic acid.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR844283X | 1956-01-25 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB844283A true GB844283A (en) | 1960-08-10 |
Family
ID=9312347
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB2306/57A Expired GB844283A (en) | 1956-01-25 | 1957-01-22 | Improvements in methods of separating uranium and thorium from each other |
Country Status (1)
| Country | Link |
|---|---|
| GB (1) | GB844283A (en) |
-
1957
- 1957-01-22 GB GB2306/57A patent/GB844283A/en not_active Expired
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