GB854235A - Improvements in the preparation of ammonium diuranate - Google Patents
Improvements in the preparation of ammonium diuranateInfo
- Publication number
- GB854235A GB854235A GB11131/59A GB1113159A GB854235A GB 854235 A GB854235 A GB 854235A GB 11131/59 A GB11131/59 A GB 11131/59A GB 1113159 A GB1113159 A GB 1113159A GB 854235 A GB854235 A GB 854235A
- Authority
- GB
- United Kingdom
- Prior art keywords
- ammonium
- ammonium diuranate
- ammonia
- diuranate
- uranium
- 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
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G43/00—Compounds of uranium
Landscapes
- Chemical & Material Sciences (AREA)
- Organic Chemistry (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Geology (AREA)
- Inorganic Chemistry (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
Ammonium diuranate having a bulk density not less than 1.4 g./ml. and having a particle size below 3 microns is prepared by precipitating finely divided ammonium diuranate from an aqueous solution containing per gallon, between 0.3 and 0.6 pounds of uranium, 0.15 and 0.3 pounds of fluoride and an excess of at least 0.3 pounds of ammonia over that stoichiometrically required to neutralise any acid present and to form ammonium diuranate. The ammonium diuranate precipitate is separated from the mother liquor without washing and the fluoride - containing ammonium diuranate is thereafter dried. It is particularly suitable for converting to uranium dioxide of bulk density of 2.4 g./ml. or more, from which high density compacts having at least 60% theoretical density may be obtained. Such compacts may be sintered to obtain uranium dioxide bodies of more than 90% theoretical density. The ammonium diuranate may be formed by hydrolising uranium hexafluoride in an ammonia solution. For example uranium hexafluoride may be added to a solution of ammonia in the mol ratio of 1 to 4 after which the required excess ammonia is rapidly added in the form of a 27% solution to precipitate the uranium diuranate. Alternatively ammonium diuranate from any source may be dissolved in a solution containing sufficient ammonium bifluoride to produce a U/F ratio of about 2 and the required excess ammonia rapidly added to precipitate the high density finely divided ammonium diuranate of the invention. Alternatively ammonium diuranate may be precipitated from a neutral solution of uranyl fluoride and ammonium fluoride by adding the required excess of ammonia thereto. Specification 850,957 is referred to.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US854235XA | 1958-04-03 | 1958-04-03 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB854235A true GB854235A (en) | 1960-11-16 |
Family
ID=22191485
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB11131/59A Expired GB854235A (en) | 1958-04-03 | 1959-04-01 | Improvements in the preparation of ammonium diuranate |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB854235A (en) |
-
1959
- 1959-04-01 GB GB11131/59A patent/GB854235A/en not_active Expired
Similar Documents
Publication | Publication Date | Title |
---|---|---|
GB1213588A (en) | A process for the production of stable silicate solutions | |
ES325259A1 (en) | Method of preparing uranium diuranate | |
DE1592535B2 (en) | Process for the production of uranyl fluoride powder | |
US2466118A (en) | Precipitation of ammonium diuranate | |
GB854235A (en) | Improvements in the preparation of ammonium diuranate | |
GB900790A (en) | Improvements in or relating to crystalline synthetic cryolite | |
NO137354B (en) | PROCEDURES FOR PROTECTING SHIPS AGAINST GROUNDING | |
US2767044A (en) | Plutonium recovery process | |
US2650153A (en) | Process for the production of ammonium uranium fluoride | |
US3333919A (en) | Strontium recovery process | |
GB856827A (en) | A process for preparing high-purity uranium values from uranium ore concentrates | |
US2761756A (en) | Process for production of uranium hexafluoride | |
US3407032A (en) | Method for preparing reduced tungsten oxide | |
US4124525A (en) | Process for working up uranium-thorium wastes | |
US2899270A (en) | Production of thorium fluoride | |
GB1206048A (en) | Process for the production of uranium dioxide | |
ES388664A1 (en) | Process for the recovery of ammonium sulphate from it aqueous solutions contaminated by organic substances | |
US2875026A (en) | Precipitation method of separating plutonium from contaminating elements | |
GB968679A (en) | Process for the direct preparation of practically spherical granular, uranium-containing material of a definite particle size | |
US2902339A (en) | Recovery of plutonium from aqueous solutions | |
GB956075A (en) | Improvements in or relating to the production of alkali metal fluoborates | |
DeptuĆa et al. | Separation of trace impurities of 131 I from 99 Mo obtained by extraction from fission products of uranium | |
US2978295A (en) | Recovery of plutonium by carrier precipitation | |
US3622480A (en) | Method of increasing the concentration of oyxgen-18 in an oxygen-containing compound | |
GB983036A (en) | Process for the reduction of uranium hexafluoride to uranium tetrafluoride |