FR2559612B1 - Procede de traitement de combustible nucleaire irradie, pour separer l'uranium du plutonium - Google Patents

Procede de traitement de combustible nucleaire irradie, pour separer l'uranium du plutonium

Info

Publication number
FR2559612B1
FR2559612B1 FR8501966A FR8501966A FR2559612B1 FR 2559612 B1 FR2559612 B1 FR 2559612B1 FR 8501966 A FR8501966 A FR 8501966A FR 8501966 A FR8501966 A FR 8501966A FR 2559612 B1 FR2559612 B1 FR 2559612B1
Authority
FR
France
Prior art keywords
plutonium
treatment
nuclear fuel
irradiated nuclear
separate uranium
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
FR8501966A
Other languages
English (en)
Other versions
FR2559612A1 (fr
Inventor
John Garraway
Peter David Wilson
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.)
Sellafield Ltd
Original Assignee
British Nuclear Fuels PLC
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 British Nuclear Fuels PLC filed Critical British Nuclear Fuels PLC
Publication of FR2559612A1 publication Critical patent/FR2559612A1/fr
Application granted granted Critical
Publication of FR2559612B1 publication Critical patent/FR2559612B1/fr
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
    • C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
    • C22B60/0221—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching
    • C22B60/0226—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors
    • C22B60/0239—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors nitric acid containing ion as active agent
    • 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
    • C22B60/0295—Obtaining thorium, uranium, or other actinides obtaining other actinides except plutonium
    • 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
FR8501966A 1984-02-13 1985-02-12 Procede de traitement de combustible nucleaire irradie, pour separer l'uranium du plutonium Expired FR2559612B1 (fr)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB8403724A GB8403724D0 (en) 1984-02-13 1984-02-13 Treating nuclear fuel

Publications (2)

Publication Number Publication Date
FR2559612A1 FR2559612A1 (fr) 1985-08-16
FR2559612B1 true FR2559612B1 (fr) 1988-10-07

Family

ID=10556502

Family Applications (1)

Application Number Title Priority Date Filing Date
FR8501966A Expired FR2559612B1 (fr) 1984-02-13 1985-02-12 Procede de traitement de combustible nucleaire irradie, pour separer l'uranium du plutonium

Country Status (7)

Country Link
US (1) US4656011A (fr)
JP (1) JPS60187897A (fr)
BE (1) BE901721A (fr)
DE (1) DE3504743A1 (fr)
FR (1) FR2559612B1 (fr)
GB (2) GB8403724D0 (fr)
IT (1) IT1182439B (fr)

Families Citing this family (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2607823B1 (fr) * 1986-12-03 1989-02-17 Commissariat Energie Atomique Procede pour separer le technetium present dans un solvant organique avec du zirconium et au moins un autre metal tel que l'uranium ou le plutonium, utilisable notamment pour le retraitement des combustibles nucleaires irradies
DE3718338A1 (de) * 1987-06-01 1989-01-05 Karlsruhe Wiederaufarbeit Verfahren und vorrichtung zur loesungsmittelwaesche bei der wiederaufarbeitung von bestrahlten kernbrennstoffen
DE3809042A1 (de) * 1988-03-18 1989-09-28 Wiederaufarbeitung Von Kernbre Verfahren und vorrichtung zum abtrennen von uran, plutonium sowie spaltprodukten
DE3843887C1 (fr) * 1988-12-24 1990-06-21 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe, De
US5077020A (en) * 1989-12-20 1991-12-31 Westinghouse Electric Corp. Metal recovery process using waterglass
DE4110128A1 (de) * 1990-04-09 1991-11-07 Westinghouse Electric Corp Dekontamination von radioaktiv verseuchten metallen
US5183541A (en) * 1990-04-09 1993-02-02 Westinghouse Electric Corp. Decontamination of radioactive metals
US5217585A (en) * 1991-12-20 1993-06-08 Westinghouse Electric Corp. Transition metal decontamination process
FR2717001B1 (fr) * 1994-03-04 1996-05-24 Japan Atomic Energy Res Inst Procédé de décontamination du technétium dans le retraitement d'un combustible nucléaire épuisé.
FR2748951B1 (fr) * 1996-05-24 1998-07-03 Commissariat Energie Atomique Procede de separation selective des actinides (iii) et lanthanides (iii)
CN103451428B (zh) * 2012-05-28 2015-03-11 中国原子能科学研究院 Purex流程钚纯化循环中钌的净化工艺
CN105761770B (zh) * 2016-04-15 2017-12-26 中国原子能科学研究院 一种采用羟胺乙酸为反萃试剂的钚纯化循环工艺

Family Cites Families (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
BE635254A (fr) * 1962-08-17 1900-01-01
FR2212611B1 (fr) * 1972-12-28 1975-11-07 Commissariat Energie Atomique
DE2449589C2 (de) * 1974-10-18 1984-09-20 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Verfahren zur Entfernung von Zersetzungsprodukten aus Extraktionsmitteln, die zur Wiederaufarbeitung abgebrannter Kernbrenn- und/oder Brutstoffe verwendet werden
US3987145A (en) * 1975-05-15 1976-10-19 The United States Of America As Represented By The United States Energy Research And Development Administration Ferric ion as a scavenging agent in a solvent extraction process
DE2838541A1 (de) * 1977-09-16 1979-04-05 British Nuclear Fuels Ltd Verfahren zur reinigung einer plutonium enthaltenden phase
US4162230A (en) * 1977-12-28 1979-07-24 The United States Of America As Represented By The United States Department Of Energy Method for the recovery of actinide elements from nuclear reactor waste
GB2050039B (en) * 1979-04-30 1983-01-19 Atomic Energy Authority Uk Dissolving plutanium containing nuclear fuels

Also Published As

Publication number Publication date
US4656011A (en) 1987-04-07
GB2154048A (en) 1985-08-29
IT8567148A1 (it) 1986-08-13
DE3504743A1 (de) 1985-09-26
JPS60187897A (ja) 1985-09-25
FR2559612A1 (fr) 1985-08-16
JPH0518076B2 (fr) 1993-03-10
IT8567148A0 (it) 1985-02-13
IT1182439B (it) 1987-10-05
GB8403724D0 (en) 1984-03-14
BE901721A (fr) 1985-05-29
GB8501857D0 (en) 1985-03-27
GB2154048B (en) 1987-11-25

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Legal Events

Date Code Title Description
ST Notification of lapse