GB1260562A - Production of uranyl fluoride - Google Patents
Production of uranyl fluorideInfo
- Publication number
- GB1260562A GB1260562A GB3845469A GB3845469A GB1260562A GB 1260562 A GB1260562 A GB 1260562A GB 3845469 A GB3845469 A GB 3845469A GB 3845469 A GB3845469 A GB 3845469A GB 1260562 A GB1260562 A GB 1260562A
- Authority
- GB
- United Kingdom
- Prior art keywords
- steam
- hydrolysis
- uranyl fluoride
- reaction zone
- fluoride
- 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
- C01G43/04—Halides of uranium
- C01G43/06—Fluorides
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
1,260,562. Uranyl fluoride. UNITED NUCLEAR CORP. 31 July, 1969, No. 38454/69. Heading C1A. Uranyl fluoride is prepared by introducing steam and gaseous UF 6 separately into a reaction zone containing fluidized uranyl fluoride particles, the UF 6 being introduced at at least 200‹ F. and 5000 c.f.h. per square inch of nozzle opening to prevent the formation of uranium fluoride solids prior to its hydrolysis with the steam, regulating the relative concentration of the UF 6 and steam in the reaction zone so that the amount of steam is above, but not in excess of 300% of, the stoichiometric requirement for the hydrolysis while maintaining the temperature in the reaction zone above 500‹ F. but below 900‹ F., maintaining sufficient uranyl fluoride seed particles in the zone to stabilize the average particle size therein and removing excess uranyl fluoride particles from the reaction zone. The hydrolysis may be carried out in the presence of an inert gaseous diluent, e.g. N 2 , CO 2 which may be used as a carrier for the gaseous UF 6 or to fluidize the bed either alone or in combination with the steam used for the hydrolysis.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB3845469A GB1260562A (en) | 1969-07-31 | 1969-07-31 | Production of uranyl fluoride |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB3845469A GB1260562A (en) | 1969-07-31 | 1969-07-31 | Production of uranyl fluoride |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1260562A true GB1260562A (en) | 1972-01-19 |
Family
ID=10403555
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB3845469A Expired GB1260562A (en) | 1969-07-31 | 1969-07-31 | Production of uranyl fluoride |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB1260562A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2184106A (en) * | 1985-12-12 | 1987-06-17 | British Nuclear Fuels Plc | Conversion of uranium hexafluoride to its tetrafluoride |
CN112811470A (en) * | 2020-11-20 | 2021-05-18 | 中核北方核燃料元件有限公司 | Method for preparing high-purity uranyl fluoride powder from uranium hexafluoride by dry method |
-
1969
- 1969-07-31 GB GB3845469A patent/GB1260562A/en not_active Expired
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2184106A (en) * | 1985-12-12 | 1987-06-17 | British Nuclear Fuels Plc | Conversion of uranium hexafluoride to its tetrafluoride |
GB2184106B (en) * | 1985-12-12 | 1989-10-18 | British Nuclear Fuels Plc | Conversion of uranium hexafluoride to its tetrafluoride |
CN112811470A (en) * | 2020-11-20 | 2021-05-18 | 中核北方核燃料元件有限公司 | Method for preparing high-purity uranyl fluoride powder from uranium hexafluoride by dry method |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
GB1280865A (en) | Production of uranium dioxide | |
ES8705526A1 (en) | Preparation of a uranium dioxide material. | |
US3906081A (en) | Fluidized reactor reduction of UF{HD 6 {B to UO{HD 2 | |
GB1392537A (en) | Process for converting uranium hexafluoride to uranium dioxide particles of a selected size | |
GB1376921A (en) | Method of and apparatus for coating particles especially nuclear fuel particles for nuclear reactors | |
GB1303894A (en) | ||
GB1353258A (en) | Process for the production of pelleted carbon black | |
GB1260562A (en) | Production of uranyl fluoride | |
GB1350923A (en) | Method for preparing oxides of fissile materials | |
GB995479A (en) | Continuous extraction of poly-e-caproamide | |
GB1206048A (en) | Process for the production of uranium dioxide | |
GB1350832A (en) | Method of calcining carbonaceous agglomerates | |
ES459152A1 (en) | Method of producing PuO2 by calcination of Pu oxalate produced by discontinuous precipitation from solutions contaminated with americium | |
SE8203745L (en) | URANE PEROXIDE IN THE FORM OF SPHERICAL PARTICLES WITH GOOD RINSE PROPERTIES AND PROCEDURE FOR PREPARING THEREOF | |
GB1439861A (en) | Fluidised bed apparatus | |
US3519403A (en) | Method for the preparation of uranium dioxide powder (uo2) with good pressing and sintering properties from uranium hexafluoride (uf6) or aqueous solutions of uranyl nitrate (uo2(no3)2) | |
US3006726A (en) | Process for upgrading crude alkali metal sulfates | |
GB1381495A (en) | Fluidized bed process and apparatus | |
GB983494A (en) | Process and apparatus for the cooling of particulate solids | |
US3340019A (en) | Process for the reprocessing of irradiated compact fuels by fluorination | |
GB1360341A (en) | Method for reducing the oxygen in certain actinide oxides to less than stoichiometric levels | |
GB1156448A (en) | Process for the production of Calcium Cyanamide | |
ES459153A1 (en) | Process for preparing americium dioxide and apparatus therefore | |
GB925848A (en) | Process for the manufacture of titanium dichloride | |
GB801288A (en) | Fuel for nuclear reactors and process of making the same |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed | ||
PLNP | Patent lapsed through nonpayment of renewal fees |