GB839749A - Separation of plutonium from solution - Google Patents

Separation of plutonium from solution

Info

Publication number
GB839749A
GB839749A GB744246A GB744246A GB839749A GB 839749 A GB839749 A GB 839749A GB 744246 A GB744246 A GB 744246A GB 744246 A GB744246 A GB 744246A GB 839749 A GB839749 A GB 839749A
Authority
GB
United Kingdom
Prior art keywords
solution
plutonium
precipitate
uranium
hydroxide
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
GB744246A
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 GB839749A publication Critical patent/GB839749A/en
Expired legal-status Critical Current

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G56/00—Compounds of transuranic elements
    • C01G56/001—Preparation involving a liquid-liquid extraction, an adsorption or an ion-exchange
    • C01G56/002—Preparation involving a liquid-liquid extraction, an adsorption or an ion-exchange by adsorption or by ion-exchange on a solid support
    • 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)
  • Organic Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Chemistry (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

839,749. Separation of plutonium. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. March 9, 1946 [March 9, 1945], No. 7442/46. Class 39(4). Plutonium is separated from solution by forming a precipitate of uranium hydroxide in the solution at a pH of at least 5À0, preferably 5À0 to 9À5, the plutonium being carried down with the uranium. The precipitate may be formed by adding a soluble uranium compound to the solution followed by sodium hydroxide, sodium bicarbonate, or ammonium hydroxide. The precipitate is separated and dissolved in nitric, sulphuric, or hydrochloric acid ; the pH of the solution is increased to a value not greater than 2À5 by addition of a base so as to precipitate uranium leaving plutonium in solution. After filtering off the uranium precipitate, plutonium may be recovered from solution by precipitation as hydroxide, iodate, or peroxide.
GB744246A 1945-03-09 1946-03-09 Separation of plutonium from solution Expired GB839749A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US839749XA 1945-03-09 1945-03-09

Publications (1)

Publication Number Publication Date
GB839749A true GB839749A (en) 1960-06-29

Family

ID=22181851

Family Applications (1)

Application Number Title Priority Date Filing Date
GB744246A Expired GB839749A (en) 1945-03-09 1946-03-09 Separation of plutonium from solution

Country Status (1)

Country Link
GB (1) GB839749A (en)

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