GB822290A - Improvements in or relating to a process for the treatment of nuclear fuel - Google Patents

Improvements in or relating to a process for the treatment of nuclear fuel

Info

Publication number
GB822290A
GB822290A GB339756A GB339756A GB822290A GB 822290 A GB822290 A GB 822290A GB 339756 A GB339756 A GB 339756A GB 339756 A GB339756 A GB 339756A GB 822290 A GB822290 A GB 822290A
Authority
GB
United Kingdom
Prior art keywords
treatment
nuclear fuel
acid
nitrous
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
GB339756A
Inventor
Geoffrey John Ashworth
Peter George Minchin Brown
John Molyneux Fletcher
Arthur Gregory Wain
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 GB339756A priority Critical patent/GB822290A/en
Priority to FR1196550D priority patent/FR1196550A/en
Priority to BE569322A priority patent/BE569322A/xx
Publication of GB822290A publication Critical patent/GB822290A/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)
  • Investigating Or Analyzing Non-Biological Materials By The Use Of Chemical Means (AREA)

Abstract

822,290. Treatment of nuclear fuel. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. Feb. 1, 1957 [Feb. 3, 1956], No. 3397/56. Class 39(4). Nuclear fuel which has been irradiated in a reactor is dissolved in nitric acid, the acid concentration of the solution adjusted to 1-5M, the solution treated with nitrous acid at 50‹-80‹C. for at least one hour, cooled to room temperature, and contacted with diluted tributyl phosphate to extract fissile material. The treatment with nitrous acid converts ruthenium present into a form less easily extracted by the organic solvent. Nitrous acid may be introduced by treating the solution with nitrous fumes or by adding sodium nitrate. Specifications 810,743 and 811,772 [both in Group III] are referred to.
GB339756A 1956-02-03 1956-02-03 Improvements in or relating to a process for the treatment of nuclear fuel Expired GB822290A (en)

Priority Applications (3)

Application Number Priority Date Filing Date Title
GB339756A GB822290A (en) 1956-02-03 1956-02-03 Improvements in or relating to a process for the treatment of nuclear fuel
FR1196550D FR1196550A (en) 1956-02-03 1958-06-02 Nuclear fuel processing process
BE569322A BE569322A (en) 1956-02-03 1958-07-10

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB339756A GB822290A (en) 1956-02-03 1956-02-03 Improvements in or relating to a process for the treatment of nuclear fuel

Publications (1)

Publication Number Publication Date
GB822290A true GB822290A (en) 1959-10-21

Family

ID=9757563

Family Applications (1)

Application Number Title Priority Date Filing Date
GB339756A Expired GB822290A (en) 1956-02-03 1956-02-03 Improvements in or relating to a process for the treatment of nuclear fuel

Country Status (3)

Country Link
BE (1) BE569322A (en)
FR (1) FR1196550A (en)
GB (1) GB822290A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3288568A (en) * 1960-11-18 1966-11-29 Tokyo Shibaura Electric Co Direct dissolution of water-insoluble uranium compounds by contact with neutral organic solvents pretreated with nitric acid
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

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3198599A (en) * 1961-09-15 1965-08-03 Allied Chem Recovery of uranium and/or vanadium values from ores containing the same

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3288568A (en) * 1960-11-18 1966-11-29 Tokyo Shibaura Electric Co Direct dissolution of water-insoluble uranium compounds by contact with neutral organic solvents pretreated with nitric acid
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

Also Published As

Publication number Publication date
FR1196550A (en) 1959-11-24
BE569322A (en) 1959-01-10

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