GB808723A - Improvements in or relating to the separation of plutonium - Google Patents

Improvements in or relating to the separation of plutonium

Info

Publication number
GB808723A
GB808723A GB818147A GB818147A GB808723A GB 808723 A GB808723 A GB 808723A GB 818147 A GB818147 A GB 818147A GB 818147 A GB818147 A GB 818147A GB 808723 A GB808723 A GB 808723A
Authority
GB
United Kingdom
Prior art keywords
plutonium
nitrate
solution
fluoride
lanthanum
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
GB818147A
Inventor
Alfred Gavin Maddock
Fred Smith
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
Priority to GB818147A priority Critical patent/GB808723A/en
Publication of GB808723A publication Critical patent/GB808723A/en
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
    • C22B60/04—Obtaining plutonium
    • 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

  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Organic Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • Environmental & Geological Engineering (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Manufacturing & Machinery (AREA)
  • Inorganic Chemistry (AREA)
  • Geology (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Solid-Sorbent Or Filter-Aiding Compositions (AREA)
  • Treatment Of Liquids With Adsorbents In General (AREA)
  • Extraction Or Liquid Replacement (AREA)

Abstract

Plutonium in a valency state not higher than quadrivalent is separated from uranium by applying an aqueous solution containing plutonium and uranium to a metal fluoride which is substantially insoluble in water and has the property of adsorbing or chemisorbing the plutonium, and subsequently recovering the plutonium from the adsorbent by treatment with an aqueous inorganic nitrate solution. The adsorbent may be calcium, lanthanum, or other rare earth fluoride, and is preferably sintered, heat treated, or aged; alternatively calcium or lanthanum fluoride may be precipitated in the solution, carrying down the plutonium. Suitable nitrate solutions are of aluminium, ferric, or manganous nitrate; the concentration of the solution may be 50 per cent or more of saturation. Plutonium may be recovered from the nitrate solution by saturating with calcium, zinc, ammonium, ferric, aluminium, or copper nitrate, followed by extraction with a water-immiscible organic solvent, e.g. nitromethane, diethyl ether, or methyl isobutyl ketone. In examples: (1) an oxidized nitrate solution containing uranium, fission products, and plutonium is passed through a column of sintered calcium fluoride to remove fission products; the effluent solution is reduced with sulphur dioxide and passed through a similar column to adsorb plutonium which is removed by treatment with ferric nitrate solution, followed by extraction with nitromethane; (2) lanthanum nitrate is added to a solution containing uranium and tervalent or quadrivalent plutonium; hydrogen fluoride is then added to precipitate lanthanum and plutonium as fluorides and the precipitate is treated with ferric nitrate solution as in Example 1. Specification 783,601 is referred to.
GB818147A 1947-03-26 1947-03-26 Improvements in or relating to the separation of plutonium Expired GB808723A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB818147A GB808723A (en) 1947-03-26 1947-03-26 Improvements in or relating to the separation of plutonium

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB818147A GB808723A (en) 1947-03-26 1947-03-26 Improvements in or relating to the separation of plutonium

Publications (1)

Publication Number Publication Date
GB808723A true GB808723A (en) 1959-02-11

Family

ID=9847395

Family Applications (1)

Application Number Title Priority Date Filing Date
GB818147A Expired GB808723A (en) 1947-03-26 1947-03-26 Improvements in or relating to the separation of plutonium

Country Status (1)

Country Link
GB (1) GB808723A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114855001A (en) * 2022-05-24 2022-08-05 中国人民解放军63653部队 Method for recovering plutonium from strong acid waste liquid

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114855001A (en) * 2022-05-24 2022-08-05 中国人民解放军63653部队 Method for recovering plutonium from strong acid waste liquid

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