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GB2118759B - Process for the recovery of plutonium from aqueous nitric solutions - Google Patents

Process for the recovery of plutonium from aqueous nitric solutions

Info

Publication number
GB2118759B
GB2118759B GB8306963A GB8306963A GB2118759B GB 2118759 B GB2118759 B GB 2118759B GB 8306963 A GB8306963 A GB 8306963A GB 8306963 A GB8306963 A GB 8306963A GB 2118759 B GB2118759 B GB 2118759B
Authority
GB
United Kingdom
Prior art keywords
plutonium
recovery
aqueous nitric
nitric solutions
solutions
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
GB8306963A
Other versions
GB8306963D0 (en
GB2118759A (en
Inventor
Heinz Dworschak
Brian A Hunt
Francis Mousty
Francesco Mannone
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.)
European Atomic Energy Community Euratom
Original Assignee
European Atomic Energy Community Euratom
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 European Atomic Energy Community Euratom filed Critical European Atomic Energy Community Euratom
Publication of GB8306963D0 publication Critical patent/GB8306963D0/en
Publication of GB2118759A publication Critical patent/GB2118759A/en
Application granted granted Critical
Publication of GB2118759B publication Critical patent/GB2118759B/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
    • 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)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Extraction Or Liquid Replacement (AREA)
GB8306963A 1982-03-15 1983-03-14 Process for the recovery of plutonium from aqueous nitric solutions Expired GB2118759B (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
LU84016A LU84016A1 (en) 1982-03-15 1982-03-15 METHOD FOR THE RECOVERY OF PLUTONIUM FROM NITROUS ACID SOLUTIONS

Publications (3)

Publication Number Publication Date
GB8306963D0 GB8306963D0 (en) 1983-04-20
GB2118759A GB2118759A (en) 1983-11-02
GB2118759B true GB2118759B (en) 1986-07-16

Family

ID=19729837

Family Applications (1)

Application Number Title Priority Date Filing Date
GB8306963A Expired GB2118759B (en) 1982-03-15 1983-03-14 Process for the recovery of plutonium from aqueous nitric solutions

Country Status (5)

Country Link
DE (1) DE3307403A1 (en)
FR (1) FR2523156A1 (en)
GB (1) GB2118759B (en)
IT (1) IT1173703B (en)
LU (1) LU84016A1 (en)

Families Citing this family (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3346405A1 (en) * 1983-12-22 1985-07-04 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe METHOD FOR THE IMPROVED SEPARATION OF THE RECOVERY OF THE URAN AND PLUTONIUM FUELS AND THE IMPROVED SEPARATION OF THE FUELS TO BE RECOVERED FROM HIM IN A REPROCESSING PROCESS
DE3546128A1 (en) * 1985-12-24 1987-07-02 Kernforschungsz Karlsruhe METHOD FOR IMPROVING A LIQUID-LIQUID EXTRACTION PROCESS
EP0251399A1 (en) * 1986-06-23 1988-01-07 "Centre d'Etude de l'Energie Nucléaire", "C.E.N." Process for separating or recovering plutonium, and plutonium obtained thereby
JP2858805B2 (en) * 1989-08-25 1999-02-17 日本原子力研究所 Reprocessing of spent nuclear fuel by low temperature and high load Purex method
RU2229178C2 (en) * 1998-08-28 2004-05-20 Бритиш Нуклеа Фюэлс ПЛС METHOD FOR RECOVERING SPENT NUCLEAR FUEL (ALTERNATIVES), Np(VI)-\lang1033\f1 TO\lang1049\f0 -Np(V) REDUCER, Pu(IV)-TO-Pu(III) REDUCER, AND JOINED Np(VI)-TO-Np(V) AND Pu(IV)-TO- (Pu(III) REDUCER
RU2171507C2 (en) * 1999-10-12 2001-07-27 Сибирский химический комбинат Method for recovering nuclear fuel enriched by fissionable material
RU2170964C1 (en) * 1999-11-16 2001-07-20 Сибирский химический комбинат Method for extractive recovery of uranium- containing solutions
RU2177651C2 (en) * 2000-02-15 2001-12-27 Открытое акционерное общество "Новосибирский завод химконцентратов" Method and plant for extracting uranium from spent filters
RU2514947C2 (en) * 2012-03-05 2014-05-10 Российская Федерация, от имени которой выступает Государственная корпорация по атомной энергии "Росатом" Method for re-extraction of plutonium from organic solution of tributyl phosphate
CN104018013B (en) * 2014-06-23 2016-01-27 中国原子能科学研究院 A method for preparing uranium-plutonium co-precipitation feed liquid by solvent extraction
CN105913887B (en) * 2016-04-14 2018-01-19 中国原子能科学研究院 It is a kind of to use formaldoxime to be stripped the plutonium purification cycle technique of reagent
FR3139408B1 (en) * 2022-09-02 2024-09-13 Commissariat Energie Atomique PROCESS FOR THE DEEXTRACTION OF URANIUM(VI) AND AN ACTINIDE(IV) FROM AN ORGANIC SOLUTION BY OXALIC PRECIPITATION

Family Cites Families (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1044085A (en) *
GB834531A (en) * 1954-12-11 1960-05-11 Atomic Energy Authority Uk Improvements in or relating to the recovery of plutonium from organic solvents
US2951740A (en) * 1957-07-26 1960-09-06 Jr Horace H Hopkins Processing of neutron-irradiated uranium
GB865669A (en) * 1958-03-21 1961-04-19 Bataafsche Petroleum Asphaltic bitumen composition
US3104940A (en) * 1958-09-02 1963-09-24 Bril Kazimierz Josef Process for the separation of thorium and uranium salts
FR1241470A (en) * 1959-01-27 1960-09-16 Atomic Energy Commission Plutonium extraction process
BE623437A (en) * 1961-10-11 1900-01-01
US3328133A (en) * 1964-02-10 1967-06-27 Japan Atomic Energy Res Inst Method for direct recovery of plutonium from irradiated nuclear fuel
US3359078A (en) * 1965-02-10 1967-12-19 Gen Electric Irradaiated nuclear fuel recovery
US3781404A (en) * 1972-05-18 1973-12-25 Atomic Energy Commission Americium recovery from reduction residues
FR2212610B1 (en) * 1972-12-28 1977-08-05 Commissariat Energie Atomique
US4025602A (en) * 1976-05-25 1977-05-24 The United States Of America As Represented By The United States Energy Research And Development Administration Recovery of transplutonium elements from nuclear reactor waste
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
US4208377A (en) * 1978-07-25 1980-06-17 The United States Of America As Represented By The United States Department Of Energy Process for recovering actinide values
DE3243841C2 (en) * 1982-11-26 1986-02-06 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Process for the denitration of nitric acid, actinide-containing waste solutions with simultaneous separation of the actinides

Also Published As

Publication number Publication date
IT8347900A1 (en) 1984-09-14
GB8306963D0 (en) 1983-04-20
GB2118759A (en) 1983-11-02
IT1173703B (en) 1987-06-24
IT8347900A0 (en) 1983-03-14
FR2523156A1 (en) 1983-09-16
DE3307403A1 (en) 1983-10-27
LU84016A1 (en) 1982-07-08

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Legal Events

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