FR1252018A - Process for extracting uranium compounds from their solutions - Google Patents

Process for extracting uranium compounds from their solutions

Info

Publication number
FR1252018A
FR1252018A FR748045A FR748045A FR1252018A FR 1252018 A FR1252018 A FR 1252018A FR 748045 A FR748045 A FR 748045A FR 748045 A FR748045 A FR 748045A FR 1252018 A FR1252018 A FR 1252018A
Authority
FR
France
Prior art keywords
solutions
uranium compounds
extracting uranium
extracting
compounds
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
FR748045A
Other languages
French (fr)
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.)
Studsvik Energiteknik AB
Original Assignee
Studsvik Energiteknik AB
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 Studsvik Energiteknik AB filed Critical Studsvik Energiteknik AB
Application granted granted Critical
Publication of FR1252018A publication Critical patent/FR1252018A/en
Expired legal-status Critical Current

Links

Classifications

    • BPERFORMING OPERATIONS; TRANSPORTING
    • B01PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01DSEPARATION
    • B01D11/00Solvent extraction
    • B01D11/04Solvent extraction of solutions which are liquid
    • B01D11/0492Applications, solvents used
    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01GCOMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00Compounds of uranium
    • 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
    • C22B60/0217Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
    • C22B60/0252Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
    • C22B60/026Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries liquid-liquid extraction with or without dissolution in organic solvents
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/42Reprocessing of irradiated fuel
    • G21C19/44Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/46Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02WCLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00Technologies for solid waste management
    • Y02W30/50Reuse, recycling or recovery technologies

Landscapes

  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Organic Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • Geology (AREA)
  • Mechanical Engineering (AREA)
  • Materials Engineering (AREA)
  • Metallurgy (AREA)
  • Manufacturing & Machinery (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Inorganic Chemistry (AREA)
  • Environmental & Geological Engineering (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Extraction Or Liquid Replacement (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
FR748045A 1956-09-26 1957-09-25 Process for extracting uranium compounds from their solutions Expired FR1252018A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
SE816628X 1956-09-26

Publications (1)

Publication Number Publication Date
FR1252018A true FR1252018A (en) 1961-01-27

Family

ID=20345539

Family Applications (1)

Application Number Title Priority Date Filing Date
FR748045A Expired FR1252018A (en) 1956-09-26 1957-09-25 Process for extracting uranium compounds from their solutions

Country Status (5)

Country Link
BE (1) BE561050A (en)
DE (1) DE1056108B (en)
FR (1) FR1252018A (en)
GB (1) GB816628A (en)
NL (1) NL98549C (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4311675A (en) * 1980-01-23 1982-01-19 Westinghouse Electric Corp. Maintaining reductive strip efficiency in uranium recovery processes
FR2642561A1 (en) * 1989-02-01 1990-08-03 Commissariat Energie Atomique Process for separating uranium(VI) from thorium(IV) which are present in an aqueous solution by means of an N,N-dialkylamide, which can be used especially for separating the uranium produced by irradiation of thorium
FR2642562B1 (en) * 1989-02-01 1991-04-05 Commissariat Energie Atomique PROCESS FOR THE EXTRACTION OF URANIUM VI AND / OR PLUTONIUM IV FROM AN ACID AQUEOUS SOLUTION USING A MIXTURE OF N, N-DIALKYLAMIDES, FOR USE IN THE TREATMENT OF IRRADIATED NUCLEAR FUELS

Also Published As

Publication number Publication date
NL98549C (en) 1900-01-01
DE1056108B (en) 1959-04-30
BE561050A (en) 1900-01-01
GB816628A (en) 1959-07-15

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