GB968037A - Improvements in or relating to the recovery of uranium values - Google Patents

Improvements in or relating to the recovery of uranium values

Info

Publication number
GB968037A
GB968037A GB2989962A GB2989962A GB968037A GB 968037 A GB968037 A GB 968037A GB 2989962 A GB2989962 A GB 2989962A GB 2989962 A GB2989962 A GB 2989962A GB 968037 A GB968037 A GB 968037A
Authority
GB
United Kingdom
Prior art keywords
nitric acid
nuclear fuel
uranium
acid solution
organic solvent
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
GB2989962A
Inventor
Benjamin Frank Warner
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
Priority to BE635794D priority Critical patent/BE635794A/xx
Application filed by UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to GB2989962A priority patent/GB968037A/en
Publication of GB968037A publication Critical patent/GB968037A/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)

Abstract

968, 037. Processing spent nuclear fuel. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. July 11, 1963 [Aug. 3, 1962], No. 29899/62. Heading G6R. In a cyclic process for recovering uranium values from irradiated nuclear fuel, an aqueous nitric acid solution containing uranium, plutonium, and fission products is contacted with an organic solvent which extracts uranium and plutonium, leaving fission products in the aqueous solution, the solvent is washed with a dilute aqueous nitric acid solution, and the wash solution is treated to remove organic solvent, fortified with nitric acid, and used to-dissolve neutron-irradiated uranium nuclear fuel. In an example, a 3N nitric acid solution is extracted with tributyl phosphate diluted with kerosene, the organic extract is stripped with 2. 4 N nitric acid, and this acid solution is washed with kerosene or steam-stripped to remove organic solvent, brought to 6 N strength, and fed to a continuously operating dissolver for nuclear fuel. Reference has been directed by the Comptroller to Specification 801, 743.
GB2989962A 1962-08-03 1962-08-03 Improvements in or relating to the recovery of uranium values Expired GB968037A (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
BE635794D BE635794A (en) 1962-08-03
GB2989962A GB968037A (en) 1962-08-03 1962-08-03 Improvements in or relating to the recovery of uranium values

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB2989962A GB968037A (en) 1962-08-03 1962-08-03 Improvements in or relating to the recovery of uranium values

Publications (1)

Publication Number Publication Date
GB968037A true GB968037A (en) 1964-08-26

Family

ID=10299005

Family Applications (1)

Application Number Title Priority Date Filing Date
GB2989962A Expired GB968037A (en) 1962-08-03 1962-08-03 Improvements in or relating to the recovery of uranium values

Country Status (2)

Country Link
BE (1) BE635794A (en)
GB (1) GB968037A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3523765A (en) * 1966-03-08 1970-08-11 Commissariat Energie Atomique Multistage process for extracting u and pu with solvent comprising tributylphosphate
FR2455565A1 (en) * 1979-04-30 1980-11-28 Atomic Energy Authority Uk PROCESS FOR ACCELERATING THE DISSOLUTION AND INCREASING THE SOLUBILITY IN NITRIC ACID OF PLUTONIUM DIOXIDE AND MIXED URANIUM / PLUTONIUM OXIDES AND THEIR RESIDUES

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3523765A (en) * 1966-03-08 1970-08-11 Commissariat Energie Atomique Multistage process for extracting u and pu with solvent comprising tributylphosphate
FR2455565A1 (en) * 1979-04-30 1980-11-28 Atomic Energy Authority Uk PROCESS FOR ACCELERATING THE DISSOLUTION AND INCREASING THE SOLUBILITY IN NITRIC ACID OF PLUTONIUM DIOXIDE AND MIXED URANIUM / PLUTONIUM OXIDES AND THEIR RESIDUES

Also Published As

Publication number Publication date
BE635794A (en) 1900-01-01

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