GB1207288A - Process for the liquid-liquid extraction of uranium and plutonium - Google Patents

Process for the liquid-liquid extraction of uranium and plutonium

Info

Publication number
GB1207288A
GB1207288A GB1381169A GB1381169A GB1207288A GB 1207288 A GB1207288 A GB 1207288A GB 1381169 A GB1381169 A GB 1381169A GB 1381169 A GB1381169 A GB 1381169A GB 1207288 A GB1207288 A GB 1207288A
Authority
GB
United Kingdom
Prior art keywords
uranium
extraction
liquid
plutonium
march
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
GB1381169A
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 GB1207288A publication Critical patent/GB1207288A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • 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
    • 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
    • Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
    • Y02P10/00—Technologies related to metal processing
    • Y02P10/20—Recycling
    • 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

Abstract

1,207,288. Recovering uranium. KERNFORSCHUNG m.b.H. GES FUER. 17 March, 1969 [23 March, 1968], No. 13811/69. Heading C1A. [Also in Division G6] Plutonium and uranium are separated from irradiated nuclear fuel by dissolving the fuel in aqueous acid, extracting both Pu and U by contact with an immiscible organic solution of a quaternary ammonium nitrate, selectively re-extracting the U into aqueous solution, and recycling part of the organic solution containing Pu to the first extraction, the remainder being treated for re-extraction of the Pu into aqueous solution. If the Pu in the original solution is in the hexavalent state, it is reduced to Pu (III) with iron (II) sulphamate, hydroxylamine, or hydrazine, and then oxidized to Pu (IV) with sodium nitrite. U is extracted with nitric acid and Pu with acetic acid containing nitric acid or with a mixture of sulphuric and nitric acids. The quaternary ammonium nitrate specified is tricapryl-methylammonium nitrate.
GB1381169A 1968-03-23 1969-03-17 Process for the liquid-liquid extraction of uranium and plutonium Expired GB1207288A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE1767044A DE1767044C3 (en) 1968-03-23 1968-03-23 Process for the chemical processing of irradiated nuclear fuel containing uranium and plutonium

Publications (1)

Publication Number Publication Date
GB1207288A true GB1207288A (en) 1970-09-30

Family

ID=5699211

Family Applications (1)

Application Number Title Priority Date Filing Date
GB1381169A Expired GB1207288A (en) 1968-03-23 1969-03-17 Process for the liquid-liquid extraction of uranium and plutonium

Country Status (3)

Country Link
DE (1) DE1767044C3 (en)
FR (1) FR2004622A1 (en)
GB (1) GB1207288A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2719035A1 (en) * 1994-04-22 1995-10-27 Cogema Plutonium concn. and extraction from aq. soln. also contg. uranium
CN103397184A (en) * 2013-07-31 2013-11-20 南昌航空大学 Method for separating uranium and iron from tertiary amine organic phase by back extraction

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6034502B2 (en) * 1977-04-05 1985-08-09 動力炉・核燃料開発事業団 Method for reducing plutonium

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2719035A1 (en) * 1994-04-22 1995-10-27 Cogema Plutonium concn. and extraction from aq. soln. also contg. uranium
CN103397184A (en) * 2013-07-31 2013-11-20 南昌航空大学 Method for separating uranium and iron from tertiary amine organic phase by back extraction
CN103397184B (en) * 2013-07-31 2014-12-03 南昌航空大学 Method for separating uranium and iron from tertiary amine organic phase by back extraction

Also Published As

Publication number Publication date
DE1767044B2 (en) 1977-10-13
DE1767044A1 (en) 1971-08-19
FR2004622A1 (en) 1969-11-28
FR2004622B1 (en) 1973-11-16
DE1767044C3 (en) 1978-06-08

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Legal Events

Date Code Title Description
PS Patent sealed
PCNP Patent ceased through non-payment of renewal fee