GB862860A - Purification of thorium or uranium, or thorium-uranium alloys - Google Patents
Purification of thorium or uranium, or thorium-uranium alloysInfo
- Publication number
- GB862860A GB862860A GB31460/58A GB3146058A GB862860A GB 862860 A GB862860 A GB 862860A GB 31460/58 A GB31460/58 A GB 31460/58A GB 3146058 A GB3146058 A GB 3146058A GB 862860 A GB862860 A GB 862860A
- Authority
- GB
- United Kingdom
- Prior art keywords
- thorium
- uranium
- electrolyte
- cathode
- salt
- 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
- C25—ELECTROLYTIC OR ELECTROPHORETIC PROCESSES; APPARATUS THEREFOR
- C25C—PROCESSES FOR THE ELECTROLYTIC PRODUCTION, RECOVERY OR REFINING OF METALS; APPARATUS THEREFOR
- C25C7/00—Constructional parts, or assemblies thereof, of cells; Servicing or operating of cells
- C25C7/02—Electrodes; Connections thereof
-
- C—CHEMISTRY; METALLURGY
- C25—ELECTROLYTIC OR ELECTROPHORETIC PROCESSES; APPARATUS THEREFOR
- C25C—PROCESSES FOR THE ELECTROLYTIC PRODUCTION, RECOVERY OR REFINING OF METALS; APPARATUS THEREFOR
- C25C3/00—Electrolytic production, recovery or refining of metals by electrolysis of melts
- C25C3/34—Electrolytic production, recovery or refining of metals by electrolysis of melts of metals not provided for in groups C25C3/02 - C25C3/32
Abstract
862,860. Electrolytic refining of thorium and uranium. UNITED STATES ATOMIC ENERGY COMMISSION. Oct. 2,1958 [Oct. 9, 1957], No. 31460/58. Class 41. Thorium, uranium, and thorium-uranium alloys are purified by electrolysis in a fused-salt electrolyte, using one of the metals zinc, cadmium, tin, lead, antimony and bismuth in molten condition as cathode. The anode may also consist of one of these molten metals, the thorium or uranium to be refined being placed in contact therewith and separated from direct contact with the electrolyte thereby. The electrolyte may be a fused alkali metal salt or alkaline-earth metal salt. A current density of 200 amps/square dm. is used. The refined metal dissolves in the molten cathode, and the cathode metal is subsequently removed therefrom by volatilization. Alternatively, the thorium or uranium may be added to the bath in the form of a salt, using a carbon anode.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US862860XA | 1957-10-09 | 1957-10-09 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB862860A true GB862860A (en) | 1961-03-15 |
Family
ID=22197555
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB31460/58A Expired GB862860A (en) | 1957-10-09 | 1958-10-02 | Purification of thorium or uranium, or thorium-uranium alloys |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB862860A (en) |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2212171A (en) * | 1987-11-05 | 1989-07-19 | Us Energy | Recovery of uranium and a mixture of uranium and plutonium from spent fuels by electrorefining |
GB2247247A (en) * | 1990-08-22 | 1992-02-26 | British Nuclear Fuels Plc | Electrolytic production of uranium alloy in molten salt electrolyte |
GB2548378A (en) * | 2016-03-16 | 2017-09-20 | Richard Scott Ian | Electrochemical reduction of spent nuclear fuel at high temperatures |
US10622112B2 (en) | 2016-03-16 | 2020-04-14 | Ian Richard Scott | Conversion of spent uranium oxide fuel into molten salt reactor fuel |
-
1958
- 1958-10-02 GB GB31460/58A patent/GB862860A/en not_active Expired
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2212171A (en) * | 1987-11-05 | 1989-07-19 | Us Energy | Recovery of uranium and a mixture of uranium and plutonium from spent fuels by electrorefining |
GB2212171B (en) * | 1987-11-05 | 1991-08-21 | Us Energy | Electrorefining process and apparatus for recovery of uranium and a mixture of uranium and plutonium from spent fuels |
GB2247247A (en) * | 1990-08-22 | 1992-02-26 | British Nuclear Fuels Plc | Electrolytic production of uranium alloy in molten salt electrolyte |
GB2548378A (en) * | 2016-03-16 | 2017-09-20 | Richard Scott Ian | Electrochemical reduction of spent nuclear fuel at high temperatures |
US10622112B2 (en) | 2016-03-16 | 2020-04-14 | Ian Richard Scott | Conversion of spent uranium oxide fuel into molten salt reactor fuel |
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