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GB838508A - Improvements in or relating to process for treating nuclear fuel - Google Patents

Improvements in or relating to process for treating nuclear fuel

Info

Publication number
GB838508A
GB838508A GB3913956A GB3913956A GB838508A GB 838508 A GB838508 A GB 838508A GB 3913956 A GB3913956 A GB 3913956A GB 3913956 A GB3913956 A GB 3913956A GB 838508 A GB838508 A GB 838508A
Authority
GB
United Kingdom
Prior art keywords
plutonium
uranium
chloride
melt
metal
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
GB3913956A
Inventor
John Keith Dawson
Allan Robert Gibson
Herbert Alan Mckay
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 GB3913956A priority Critical patent/GB838508A/en
Priority to FR1188891D priority patent/FR1188891A/en
Priority to DEU5008A priority patent/DE1058747B/en
Publication of GB838508A publication Critical patent/GB838508A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/42Reprocessing of irradiated fuel
    • G21C19/44Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/48Non-aqueous processes
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02WCLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00Technologies for solid waste management
    • Y02W30/50Reuse, 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)
  • Manufacture And Refinement Of Metals (AREA)
  • Extraction Or Liquid Replacement (AREA)

Abstract

Fission products are separated from irradiated uranium or plutonium by introducing the irradiated material into a melt of the chloride of another metal, which is displaceable by the uranium or plutonium, separating the molten chloride of uranium or plutonium from the other metal, and introducing aluminium into the melt to displace the uranium or plutonium. As described in Specification 760,217, molten lead chloride or zinc chloride may be employed, alkali metal chloride preferably also being added to the melt. The uranium or plutonium may be further purified by heating, e.g. to 1200 DEG C., to volatilize rare earth metal fission products. According to the Provisional Specification, magnesium may be used in place of aluminium.
GB3913956A 1956-12-22 1956-12-22 Improvements in or relating to process for treating nuclear fuel Expired GB838508A (en)

Priority Applications (3)

Application Number Priority Date Filing Date Title
GB3913956A GB838508A (en) 1956-12-22 1956-12-22 Improvements in or relating to process for treating nuclear fuel
FR1188891D FR1188891A (en) 1956-12-22 1957-12-20 Nuclear fuel processing process
DEU5008A DE1058747B (en) 1956-12-22 1957-12-21 Process for separating fission products from uranium or plutonium which has been exposed to radiation in a nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB3913956A GB838508A (en) 1956-12-22 1956-12-22 Improvements in or relating to process for treating nuclear fuel

Publications (1)

Publication Number Publication Date
GB838508A true GB838508A (en) 1960-06-22

Family

ID=10407855

Family Applications (1)

Application Number Title Priority Date Filing Date
GB3913956A Expired GB838508A (en) 1956-12-22 1956-12-22 Improvements in or relating to process for treating nuclear fuel

Country Status (3)

Country Link
DE (1) DE1058747B (en)
FR (1) FR1188891A (en)
GB (1) GB838508A (en)

Also Published As

Publication number Publication date
FR1188891A (en) 1959-09-25
DE1058747B (en) 1959-06-04

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