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 same

Info

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
Application number
GB25978/56A
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.)
Horizons Titanium Corp
Original Assignee
Horizons Titanium Corp
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 Horizons Titanium Corp filed Critical Horizons Titanium Corp
Publication of GB799344A publication Critical patent/GB799344A/en
Expired legal-status Critical Current

Links

Classifications

    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01GCOMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00Compounds of uranium
    • C01G43/04Halides of uranium
    • C01G43/08Chlorides

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.
GB25978/56A 1955-09-21 1956-08-24 Method of preparation of uranium chloride and fusible electrolytes containing the same Expired GB799344A (en)

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)

* Cited by examiner, † Cited by third party
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

Cited By (5)

* Cited by examiner, † Cited by third party
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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