GB805302A - Separation of plutonium - Google Patents

Separation of plutonium

Info

Publication number
GB805302A
GB805302A GB3012347A GB3012347A GB805302A GB 805302 A GB805302 A GB 805302A GB 3012347 A GB3012347 A GB 3012347A GB 3012347 A GB3012347 A GB 3012347A GB 805302 A GB805302 A GB 805302A
Authority
GB
United Kingdom
Prior art keywords
plutonium
uranium
aqueous
solvent
solution
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
GB3012347A
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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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 UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Publication of GB805302A publication Critical patent/GB805302A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/42Reprocessing of irradiated fuel
    • G21C19/44Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/46Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
    • BPERFORMING OPERATIONS; TRANSPORTING
    • B01PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01DSEPARATION
    • B01D11/00Solvent extraction
    • B01D11/04Solvent extraction of solutions which are liquid
    • B01D11/0492Applications, solvents used
    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01GCOMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G56/00Compounds of transuranic elements
    • C01G56/001Preparation involving a liquid-liquid extraction, an adsorption or an ion-exchange
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02WCLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00Technologies for solid waste management
    • Y02W30/50Reuse, recycling or recovery technologies

Landscapes

  • Chemical & Material Sciences (AREA)
  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Organic Chemistry (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Chemistry (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

Plutonium is extracted from an aqueous nitrate solution, in which it is present together with uranium and/or fission products, by treating the solution with triglycoldichloride containing a saturated aliphatic aldehyde having at least two carbon atoms per molecule, benzaldehyde, or a polyhydric phenol having hydroxyl groups in the ortho or para positions. Plutonium passes into the solvent phase in preference to uranium and fission products, which remain in the aqueous phase. The solution treated may be obtained by dissolving neutron-irradiated uranium in nitric acid, adjusting the acidity to 1 to 3N, and adding ammonium, calcium, or magnesium nitrate. Tables show the effect on the distribution coefficient of plutonium between the aqueous and solvent phases of adding to the solvent small amounts of acetaldehyde, propionaldehyde, n- and iso-butyraldehyde, benzaldehyde, hydroquinone, 2,5 - dichlorohydroquinone, catechol, and pyrogallol.
GB3012347A 1947-05-19 1947-11-12 Separation of plutonium Expired GB805302A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CA805302X 1947-05-19

Publications (1)

Publication Number Publication Date
GB805302A true GB805302A (en) 1958-12-03

Family

ID=4172531

Family Applications (1)

Application Number Title Priority Date Filing Date
GB3012347A Expired GB805302A (en) 1947-05-19 1947-11-12 Separation of plutonium

Country Status (1)

Country Link
GB (1) GB805302A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2640888A1 (en) * 1988-12-24 1990-06-29 Kernforschungsz Karlsruhe

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2640888A1 (en) * 1988-12-24 1990-06-29 Kernforschungsz Karlsruhe

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