GB816628A - A method of extracting uranium compounds from their solutions - Google Patents

A method of extracting uranium compounds from their solutions

Info

Publication number
GB816628A
GB816628A GB2943057A GB2943057A GB816628A GB 816628 A GB816628 A GB 816628A GB 2943057 A GB2943057 A GB 2943057A GB 2943057 A GB2943057 A GB 2943057A GB 816628 A GB816628 A GB 816628A
Authority
GB
United Kingdom
Prior art keywords
solution
aqueous
solutions
carbamide
extracted
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
GB2943057A
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
Publication of GB816628A publication Critical patent/GB816628A/en
Expired legal-status Critical Current

Links

Classifications

    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01D—SEPARATION
    • B01D11/00—Solvent extraction
    • B01D11/04—Solvent extraction of solutions which are liquid
    • B01D11/0492—Applications, solvents used
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00—Compounds of uranium
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02—Obtaining thorium, uranium, or other actinides
    • C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
    • C22B60/0252—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
    • C22B60/026—Obtaining 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements 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
    • G21C19/42—Reprocessing of irradiated fuel
    • G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
    • Y—GENERAL 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors
    • Y—GENERAL 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00—Technologies for solid waste management
    • Y02W30/50—Reuse, recycling or recovery technologies

Landscapes

  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Organic Chemistry (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Geology (AREA)
  • Physics & Mathematics (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • General Engineering & Computer Science (AREA)
  • Inorganic Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • Environmental & Geological Engineering (AREA)
  • Manufacturing & Machinery (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Extraction Or Liquid Replacement (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

Hexavalent uranium salts are extracted from solution in organic liquids by means of an aqueous solution of an amide, e.g. acetamide or carbamide. The final aqueous extract may then be heated as described and claimed in Specification 785,997 to precipitate uranium as ammonium uranate. In an example, an aqueous solution of uranyl nitrate was shaken with a kerosene solution of tributyl phosphate the aqueous phase separated and the organic phase re-extracted with successive portions of (a) dilute nitric acid or (b) a carbamide solution. The latter solution is the more efficient.
GB2943057A 1956-09-26 1957-09-18 A method of extracting uranium compounds from their solutions Expired GB816628A (en)

Applications Claiming Priority (1)

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

Publications (1)

Publication Number Publication Date
GB816628A true GB816628A (en) 1959-07-15

Family

ID=20345539

Family Applications (1)

Application Number Title Priority Date Filing Date
GB2943057A Expired GB816628A (en) 1956-09-26 1957-09-18 A method of 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)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2476138A1 (en) * 1980-01-23 1981-08-21 Wyoming Mineral Corp PROCESS FOR THE RECOVERY OF URANIUM FROM WET PROCESS PHOSPHORIC ACID, TO MAINTAIN THE EFFICIENCY OF FERRIC IONS
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
FR2642562A1 (en) * 1989-02-01 1990-08-03 Commissariat Energie Atomique PROCESS FOR THE EXTRACTION OF URANIUM VI AND / OR PLUTONIUM IV IN AQUEOUS ACIDIC SOLUTION USING A MIXTURE OF N, N-DIALKYLAMIDES, USEFUL FOR THE REPAIR OF IRRADIATED NUCLEAR FUELS

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2476138A1 (en) * 1980-01-23 1981-08-21 Wyoming Mineral Corp PROCESS FOR THE RECOVERY OF URANIUM FROM WET PROCESS PHOSPHORIC ACID, TO MAINTAIN THE EFFICIENCY OF FERRIC IONS
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
FR2642562A1 (en) * 1989-02-01 1990-08-03 Commissariat Energie Atomique PROCESS FOR THE EXTRACTION OF URANIUM VI AND / OR PLUTONIUM IV IN AQUEOUS ACIDIC SOLUTION USING A MIXTURE OF N, N-DIALKYLAMIDES, USEFUL FOR THE REPAIR OF IRRADIATED NUCLEAR FUELS
EP0381579A1 (en) * 1989-02-01 1990-08-08 Commissariat A L'energie Atomique Method of extracting uranium (VI) and/or plutonium (IV) present in an aqueous acid solution by means of a mixture of N,N-dialkyl amides, for use in the reprocessing of irradiated nuclear fuels
US5132092A (en) * 1989-02-01 1992-07-21 Commissariat A L'energie Atomique Process for the extraction of uranium (vi) and/or plutonium (iv) present in an acid aqueous solution by means of a mixture of n,n-dialkyl amides usable for the reprocessing of irradiated nuclear fuels

Also Published As

Publication number Publication date
NL98549C (en) 1900-01-01
DE1056108B (en) 1959-04-30
FR1252018A (en) 1961-01-27
BE561050A (en) 1900-01-01

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