GB879041A - Improvements in or relating to the processing of nuclear reactor fuel elements - Google Patents

Improvements in or relating to the processing of nuclear reactor fuel elements

Info

Publication number
GB879041A
GB879041A GB151159A GB151159A GB879041A GB 879041 A GB879041 A GB 879041A GB 151159 A GB151159 A GB 151159A GB 151159 A GB151159 A GB 151159A GB 879041 A GB879041 A GB 879041A
Authority
GB
United Kingdom
Prior art keywords
nuclear reactor
solution
reactor fuel
relating
processing
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
GB151159A
Inventor
John Arnold Williams
Leonard Lowes
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 GB151159A priority Critical patent/GB879041A/en
Publication of GB879041A publication Critical patent/GB879041A/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)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Compounds Of Alkaline-Earth Elements, Aluminum Or Rare-Earth Metals (AREA)

Abstract

In a process for recovery of uranium from an irradiated nuclear reactor fuel element also containing aluminium and silicon, the fuel element is dissolved in a limited quantity of nitric acid to give a solution containing less than the stoichiometric equivalent of nitrate ions for the cations present and containing aluminium in the basic hydroxide form, and then uranyl nitrate is extracted from the solution with an organic solvent. Preferably the solution has an acid deficiency between 0.6 M and 2 M, i.e. lacks 0.6 to 2 moles of nitrate ions per litre for stoichiometric equivalence with the cations present. Examples are given.
GB151159A 1959-01-15 1959-01-15 Improvements in or relating to the processing of nuclear reactor fuel elements Expired GB879041A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB151159A GB879041A (en) 1959-01-15 1959-01-15 Improvements in or relating to the processing of nuclear reactor fuel elements

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB151159A GB879041A (en) 1959-01-15 1959-01-15 Improvements in or relating to the processing of nuclear reactor fuel elements

Publications (1)

Publication Number Publication Date
GB879041A true GB879041A (en) 1961-10-04

Family

ID=9723241

Family Applications (1)

Application Number Title Priority Date Filing Date
GB151159A Expired GB879041A (en) 1959-01-15 1959-01-15 Improvements in or relating to the processing of nuclear reactor fuel elements

Country Status (1)

Country Link
GB (1) GB879041A (en)

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