GB799344A - Method of preparation of uranium chloride and fusible electrolytes containing the same - Google Patents
Method of preparation of uranium chloride and fusible electrolytes containing the sameInfo
- Publication number
- GB799344A GB799344A GB25978/56A GB2597856A GB799344A GB 799344 A GB799344 A GB 799344A GB 25978/56 A GB25978/56 A GB 25978/56A GB 2597856 A GB2597856 A GB 2597856A GB 799344 A GB799344 A GB 799344A
- Authority
- GB
- United Kingdom
- Prior art keywords
- uranium
- melt
- hydrogen chloride
- chloride
- uranyl nitrate
- 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
- C01G43/08—Chlorides
Landscapes
- Chemical & Material Sciences (AREA)
- Organic Chemistry (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Geology (AREA)
- Inorganic Chemistry (AREA)
- Electrolytic Production Of Metals (AREA)
Abstract
Uranium chloride free from oxygen is produced by introducing into a fused salt bath consisting of one or more of the alkali metal and alkaline earth metal (including magnesium) chlorides, uranium oxide or uranium compounds such as the nitrate, carbonate oxalate, acetate, or other organic salts, which at the temperature of the bath will decompose to give the oxide, and then treating the fused mass with a chlorinating agent, which is preferably gaseous, such as hydrogen chloride, phosgene, carbon tetrachloride, or chlorine in admixture with either carbon monoxide or carbon. The uranium chloride may either be extracted from the melt by conventional techniques, or the melt may be used for the production of uranium by electrolysis. In examples, a eutectic mixture of sodium and potassium chlorides was melted at 700 DEG C. and hydrogen chloride bubbled through the melt. Uranyl nitrate, which may be partially decomposed by prior heating, was added to the melt in small portions, the hydrogen chloride passing through the melt continuously. Alternatively, the sodium and potassium chlorides were mixed with about two thirds of the uranyl nitrate and this mixture was then melted and hydrogen chloride passed in. The remainder of the uranyl nitrate was then added as before.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US799344XA | 1955-09-21 | 1955-09-21 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB799344A true GB799344A (en) | 1958-08-06 |
Family
ID=22153745
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB25978/56A Expired GB799344A (en) | 1955-09-21 | 1956-08-24 | Method of preparation of uranium chloride and fusible electrolytes containing the same |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB799344A (en) |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE1159920B (en) * | 1960-06-28 | 1963-12-27 | Atomic Energy Commission | Process for the separation of uranium oxides from the oxides of thorium and / or plutonium |
DE1161545B (en) * | 1960-08-22 | 1964-01-23 | Atomic Energy Commission | Extraction of a mixture of uranium dioxide and plutonium dioxide enriched in plutonium |
DE1163306B (en) * | 1959-09-25 | 1964-02-20 | Atomic Energy Authority Uk | Process for the production of pure uranium dioxide from contaminated uranium oxides |
CN104562089A (en) * | 2014-10-17 | 2015-04-29 | 中国原子能科学研究院 | Method for preparing initial molten salt system in molten salt electrolysis dry after-treatment process |
-
1956
- 1956-08-24 GB GB25978/56A patent/GB799344A/en not_active Expired
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE1163306B (en) * | 1959-09-25 | 1964-02-20 | Atomic Energy Authority Uk | Process for the production of pure uranium dioxide from contaminated uranium oxides |
DE1159920B (en) * | 1960-06-28 | 1963-12-27 | Atomic Energy Commission | Process for the separation of uranium oxides from the oxides of thorium and / or plutonium |
DE1161545B (en) * | 1960-08-22 | 1964-01-23 | Atomic Energy Commission | Extraction of a mixture of uranium dioxide and plutonium dioxide enriched in plutonium |
CN104562089A (en) * | 2014-10-17 | 2015-04-29 | 中国原子能科学研究院 | Method for preparing initial molten salt system in molten salt electrolysis dry after-treatment process |
CN104562089B (en) * | 2014-10-17 | 2017-03-22 | 中国原子能科学研究院 | Method for preparing initial molten salt system in molten salt electrolysis dry after-treatment process |
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