GB862860A - Purification of thorium or uranium, or thorium-uranium alloys - Google Patents

Purification of thorium or uranium, or thorium-uranium alloys

Info

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
Application number
GB31460/58A
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
US Atomic Energy Commission (AEC)
Original Assignee
US Atomic Energy Commission (AEC)
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by US Atomic Energy Commission (AEC) filed Critical US Atomic Energy Commission (AEC)
Publication of GB862860A publication Critical patent/GB862860A/en
Expired legal-status Critical Current

Links

Classifications

    • CCHEMISTRY; METALLURGY
    • C25ELECTROLYTIC OR ELECTROPHORETIC PROCESSES; APPARATUS THEREFOR
    • C25CPROCESSES FOR THE ELECTROLYTIC PRODUCTION, RECOVERY OR REFINING OF METALS; APPARATUS THEREFOR
    • C25C7/00Constructional parts, or assemblies thereof, of cells; Servicing or operating of cells
    • C25C7/02Electrodes; Connections thereof
    • CCHEMISTRY; METALLURGY
    • C25ELECTROLYTIC OR ELECTROPHORETIC PROCESSES; APPARATUS THEREFOR
    • C25CPROCESSES FOR THE ELECTROLYTIC PRODUCTION, RECOVERY OR REFINING OF METALS; APPARATUS THEREFOR
    • C25C3/00Electrolytic production, recovery or refining of metals by electrolysis of melts
    • C25C3/34Electrolytic 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.
GB31460/58A 1957-10-09 1958-10-02 Purification of thorium or uranium, or thorium-uranium alloys Expired GB862860A (en)

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)

* Cited by examiner, † Cited by third party
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

Cited By (5)

* Cited by examiner, † Cited by third party
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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