FR2591910B1 - Procede pour l'amelioration d'un procede d'extraction liquide-liquide, notamment pour l'extraction de matiere fissible dans le retraitement de combustibles nucleaires - Google Patents

Procede pour l'amelioration d'un procede d'extraction liquide-liquide, notamment pour l'extraction de matiere fissible dans le retraitement de combustibles nucleaires

Info

Publication number
FR2591910B1
FR2591910B1 FR8617189A FR8617189A FR2591910B1 FR 2591910 B1 FR2591910 B1 FR 2591910B1 FR 8617189 A FR8617189 A FR 8617189A FR 8617189 A FR8617189 A FR 8617189A FR 2591910 B1 FR2591910 B1 FR 2591910B1
Authority
FR
France
Prior art keywords
liquid
extraction
improving
processing
nuclear fuels
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 - Fee Related
Application number
FR8617189A
Other languages
English (en)
Other versions
FR2591910A1 (fr
Inventor
Zdenek Kolarik
Ulrich Galla
Klaus Roth
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.)
Forschungszentrum Karlsruhe GmbH
Original Assignee
Kernforschungszentrum Karlsruhe GmbH
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 Kernforschungszentrum Karlsruhe GmbH filed Critical Kernforschungszentrum Karlsruhe GmbH
Publication of FR2591910A1 publication Critical patent/FR2591910A1/fr
Application granted granted Critical
Publication of FR2591910B1 publication Critical patent/FR2591910B1/fr
Anticipated expiration legal-status Critical
Expired - Fee Related 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
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Extraction Or Liquid Replacement (AREA)
FR8617189A 1985-12-24 1986-12-09 Procede pour l'amelioration d'un procede d'extraction liquide-liquide, notamment pour l'extraction de matiere fissible dans le retraitement de combustibles nucleaires Expired - Fee Related FR2591910B1 (fr)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE19853546128 DE3546128A1 (de) 1985-12-24 1985-12-24 Verfahren zur verbesserung eines fluessig-fluessig-extraktionsprozesses

Publications (2)

Publication Number Publication Date
FR2591910A1 FR2591910A1 (fr) 1987-06-26
FR2591910B1 true FR2591910B1 (fr) 1990-06-15

Family

ID=6289580

Family Applications (1)

Application Number Title Priority Date Filing Date
FR8617189A Expired - Fee Related FR2591910B1 (fr) 1985-12-24 1986-12-09 Procede pour l'amelioration d'un procede d'extraction liquide-liquide, notamment pour l'extraction de matiere fissible dans le retraitement de combustibles nucleaires

Country Status (5)

Country Link
US (1) US4787979A (fr)
JP (1) JPS62168502A (fr)
DE (1) DE3546128A1 (fr)
FR (1) FR2591910B1 (fr)
GB (1) GB2184956B (fr)

Families Citing this family (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2218651A (en) * 1988-05-18 1989-11-22 British Nuclear Fuels Plc Solvent extraction contactors
JP2726375B2 (ja) * 1993-08-13 1998-03-11 動力炉・核燃料開発事業団 ＰｕおよびＮｐ含有硝酸溶液からのＰｕとＮｐの分離回収方法
US5368829A (en) * 1993-09-09 1994-11-29 Westinghouse Electric Corporation Continuous ash extraction process
US5463177A (en) * 1994-08-23 1995-10-31 General Electric Company Solvent extraction process
FR2862804B1 (fr) * 2003-11-20 2006-01-13 Commissariat Energie Atomique Procede de separation de l'uranium (vi) d'actinides (iv) et/ou (vi)et ses utilisations
FR2880180B1 (fr) * 2004-12-29 2007-03-02 Cogema Perfectionnement du procede purex et ses utilisations
FR2903025B1 (fr) 2006-07-03 2008-10-10 Cogema Procede pour separer un element chimique de l'uranium a partir d'une phase aqueuse acide, dans un cycle d'extraction de l'uranium
CN104841162A (zh) * 2015-04-24 2015-08-19 常州大学 圆筒型恒界面萃取池

Family Cites Families (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3714324A (en) * 1968-06-18 1973-01-30 Gen Electric Irradiated fuel recovery system
DE2033748A1 (en) * 1970-07-08 1972-01-20 Feld & Hahn, 5413 Bendorf Continuous extraction/neutralisation - of acids or bases in non-aq media, using oscillating rotary stirrer
US4002716A (en) * 1973-08-23 1977-01-11 Westinghouse Electric Corporation Sulfide precipitation method of separating uranium from group II and group III metal ions
US3966872A (en) * 1973-11-01 1976-06-29 Westinghouse Electric Corporation Coupled cationic and anionic method of separating uranium
US4385037A (en) * 1980-05-16 1983-05-24 Unc Recovery Corporation Concentrated sulphuric acid treatment of an alkylphenyl acid phosphate extractant
LU84016A1 (de) * 1982-03-15 1982-07-08 Euratom Verfahren zur rueckgewinnung von plutonium aus salpetersauren waessrigen loesungen
US4548711A (en) * 1982-09-02 1985-10-22 Phillips Petroleum Company Solvent extraction
DE3332954A1 (de) * 1983-09-13 1985-03-28 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Verfahren zur abtrennung von neptunium aus einer organischen phase bei der wiederaufarbeitung bestrahlter kernbrenn- und/oder brutstoffe

Also Published As

Publication number Publication date
GB2184956A (en) 1987-07-08
FR2591910A1 (fr) 1987-06-26
GB8630738D0 (en) 1987-02-04
DE3546128A1 (de) 1987-07-02
GB2184956B (en) 1989-10-11
JPS62168502A (ja) 1987-07-24
US4787979A (en) 1988-11-29
DE3546128C2 (fr) 1991-10-17

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Legal Events

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