GB1154875A - Method of Extracting Metal Values, especially Fissile Nuclear Materials, by means of an Organic Extraction Mixture - Google Patents

Method of Extracting Metal Values, especially Fissile Nuclear Materials, by means of an Organic Extraction Mixture

Info

Publication number
GB1154875A
GB1154875A GB4279366A GB4279366A GB1154875A GB 1154875 A GB1154875 A GB 1154875A GB 4279366 A GB4279366 A GB 4279366A GB 4279366 A GB4279366 A GB 4279366A GB 1154875 A GB1154875 A GB 1154875A
Authority
GB
United Kingdom
Prior art keywords
extraction
metal values
sept
organic
extraction mixture
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
GB4279366A
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.)
Gesellschaft fuer Kernforschung mbH
Original Assignee
Gesellschaft fuer Kernforschung mbH
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 Gesellschaft fuer Kernforschung mbH filed Critical Gesellschaft fuer Kernforschung mbH
Publication of GB1154875A publication Critical patent/GB1154875A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • C22B60/0291—Obtaining thorium, uranium, or other actinides obtaining thorium
    • 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
    • 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
    • C22B60/04—Obtaining plutonium
    • 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

  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Manufacturing & Machinery (AREA)
  • Geology (AREA)
  • Materials Engineering (AREA)
  • Environmental & Geological Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Extraction Or Liquid Replacement (AREA)
  • Organic Low-Molecular-Weight Compounds And Preparation Thereof (AREA)

Abstract

1,154,875. Extraction of Th and U. GESELL- 8CHAPT FUER KERNFORSCHUNG m.b.H. 26 Sept., 1966 [25 Sept., 1965], No. 42793/66. Heading C1A. [Also in Division G6] In the extraction of metal values, especially U, Pu and Th, from aqueous solution by means of an organic solvent comprising a phosphoric acid ester, an amine, or an organic ammonium compound and an inert organic diluent, a carboxylic acid derivative is added to the solvent to improve separation into two phases. Extracting agents referred to are tributyl phosphate and tricapryl methyl ammonium nitrate. The diluent may be an aliphatic, aromatic, or halogenated hydrocarbon, e.g. dodecane or a high boiling mixture of aromatic hydrocarbons. Specified carboxylic acid derivatives are adipic dinitrile, amyl acetate, and N,N-dimethyl caprylic acid amide. Examples relate to the extraction of thorium.
GB4279366A 1965-09-25 1966-09-26 Method of Extracting Metal Values, especially Fissile Nuclear Materials, by means of an Organic Extraction Mixture Expired GB1154875A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DEG0044798 1965-09-25

Publications (1)

Publication Number Publication Date
GB1154875A true GB1154875A (en) 1969-06-11

Family

ID=7127559

Family Applications (1)

Application Number Title Priority Date Filing Date
GB4279366A Expired GB1154875A (en) 1965-09-25 1966-09-26 Method of Extracting Metal Values, especially Fissile Nuclear Materials, by means of an Organic Extraction Mixture

Country Status (3)

Country Link
DE (1) DE1592415C3 (en)
FR (1) FR1508141A (en)
GB (1) GB1154875A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
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
CN113667843A (en) * 2020-05-13 2021-11-19 厦门稀土材料研究所 Method for separating thorium by using eutectic solvent

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4530963A (en) * 1982-08-20 1985-07-23 Devoe-Holbein International, N.V. Insoluble chelating compositions

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
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
CN113667843A (en) * 2020-05-13 2021-11-19 厦门稀土材料研究所 Method for separating thorium by using eutectic solvent

Also Published As

Publication number Publication date
DE1592415C3 (en) 1976-01-02
DE1592415B2 (en) 1975-05-28
FR1508141A (en) 1968-01-05
DE1592415A1 (en) 1970-07-30

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