GB824579A - Uranium and zirconium recovery as uranium hexafluoride and zirconium fluoride from alloys containing these elements - Google Patents

Uranium and zirconium recovery as uranium hexafluoride and zirconium fluoride from alloys containing these elements

Info

Publication number
GB824579A
GB824579A GB27080/57A GB2708057A GB824579A GB 824579 A GB824579 A GB 824579A GB 27080/57 A GB27080/57 A GB 27080/57A GB 2708057 A GB2708057 A GB 2708057A GB 824579 A GB824579 A GB 824579A
Authority
GB
United Kingdom
Prior art keywords
zirconium
uranium
fluoride
bromine
uranium hexafluoride
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
GB27080/57A
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 GB824579A publication Critical patent/GB824579A/en
Expired legal-status Critical Current

Links

Classifications

    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22BPRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02Obtaining thorium, uranium, or other actinides
    • C22B60/0204Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0213Obtaining thorium, uranium, or other actinides obtaining uranium by dry processes
    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01GCOMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G25/00Compounds of zirconium
    • C01G25/04Halides
    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01GCOMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00Compounds of uranium
    • C01G43/04Halides of uranium
    • C01G43/06Fluorides

Landscapes

  • Chemical & Material Sciences (AREA)
  • Organic Chemistry (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Geology (AREA)
  • Inorganic Chemistry (AREA)
  • Environmental & Geological Engineering (AREA)
  • Manufacturing & Machinery (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

<PICT:0824579/III/1> Fluorides of uranium and zirconium are prepared by dissolving a uranium-zirconium alloy in a molten zirconium tetrafluoride-sodium fluoride mixture and treating the molten mixture with a gaseous fluorinating agent. Zirconium fluoride remains in the melt and uranium hexafluoride; together with fluorides of niobium and ruthenium, for example, are volatilized. Equimolar amounts of zirconium and sodium fluoride are preferably employed and the temperature is normally between 500 DEG and 600 DEG C. Suitable fluorinating agents are bromine penta- and trichloride, chlorine trifluoride and fluorine. Alternatively a two-stage fluorination may be effected whereby the alloy in the molten fluoride bath is first treated with hydrogen fluoride at 500-800 DEG C. to form uranium and zirconium tetrafluorides and the bath is then treated with the above mentioned fluorinating agents to produce and volatilize uranium hexafluoride. If fluorine is employed to form the uranium hexafluoride from the tetrafluoride, lead fluoride may be added to the melt in an amount of about 5 mol. per cent. The fluorine may then be diluted with an inert gas such as helium. The apparatus may be as shown in the Figure where a refractory furnace 1 is provided with a nickel insert vessel 4 which contains the molten salt mixture 8. The alloy 9 is placed in the melt and hydrogen fluoride is passed in from line 12 thereby dissolving the alloy to form tetrafluorides. Excess hydrogen fluoride is collected in cold traps 17 and 18 and thereafter fresh traps are connected and bromine pentafluoride passed through the melt. Uranium hexafluoride and excess bromine pentafluoride and bromine trifluoride reaction products were condensed in condensers 17 and 18 whilst niobium and ruthenium condensed in the earlier portions of the pipe 16. The uranium hexafluoride condensate was freed from bromine compounds by passing fluorine gas through the condensate to convert bromine compounds to the pentafluoride which may be distilled off at 45 DEG C. The decontaminated uranium hexafluoride may be further purified by vaporizing it and passing the vapour thereof over a bed of solid sodium fluoride at 100-400 DEG C.
GB27080/57A 1956-09-28 1957-08-28 Uranium and zirconium recovery as uranium hexafluoride and zirconium fluoride from alloys containing these elements Expired GB824579A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US824579XA 1956-09-28 1956-09-28

Publications (1)

Publication Number Publication Date
GB824579A true GB824579A (en) 1959-12-02

Family

ID=22171343

Family Applications (1)

Application Number Title Priority Date Filing Date
GB27080/57A Expired GB824579A (en) 1956-09-28 1957-08-28 Uranium and zirconium recovery as uranium hexafluoride and zirconium fluoride from alloys containing these elements

Country Status (2)

Country Link
FR (1) FR1182899A (en)
GB (1) GB824579A (en)

Also Published As

Publication number Publication date
FR1182899A (en) 1959-06-30

Similar Documents

Publication Publication Date Title
CA1062880A (en) Process for the disposal of alkali metals
Zong et al. Preparation of high-purity molten FLiNaK salt by the hydrofluorination process
NO141052B (en) CURABLE EPOXY RESIN MIXTURES.
Cathers Uranium recovery for spent fuel by dissolution in fused salt and fluorination
GB824579A (en) Uranium and zirconium recovery as uranium hexafluoride and zirconium fluoride from alloys containing these elements
GB927735A (en) Preparation of uranium compounds
US3278387A (en) Fuel recycle system in a molten salt reactor
US3243256A (en) Processes for the dissolution of uranium in nitric acid
Tananaev et al. The chemistry of uranium fluorides
US3395991A (en) Recovery of protactinium from molten fluoride salts
GB891436A (en) Separation of uranium and circonium
Crouse Fluorine: a key enabling element in the nuclear fuel cycle
US3310500A (en) Distillation method for reprocessing molten salt reactor fuels
US3192016A (en) Xenon hexafluoride and method of making
Hubberstey et al. Solubilities of non-metals in liquid lithium-a review
US3145078A (en) Method of reprocessing nuclear fuel elements
KR0161958B1 (en) Method for producing uranium tetrachloride from uranium oxide
US3003847A (en) Process of recovering uranium values
GB833580A (en) Process for obtaining anhydrous fluorides
Wiswall Jr et al. THE NITROFLUOR PROCESS STATUS REPORT AND PRELIMINARY APPRAISAL
US2822239A (en) Method of separating plutonium
GB1284071A (en) A method of decontaminating uranium
Yanagi et al. Behaviors of Impurities in Liquid Sodium,(III) Molten Salt Extraction for Removing Hydrogen from Liquid Sodium
US3372998A (en) Reprocessing of spent uranium fuel by means of chlorination and fractional absorption by barium chloride
GB981044A (en) Method of treating partly used nuclear fuels