GB841860A - Improvements in or relating to nuclear fuel processing - Google Patents

Improvements in or relating to nuclear fuel processing

Info

Publication number
GB841860A
GB841860A GB3516157A GB3516157A GB841860A GB 841860 A GB841860 A GB 841860A GB 3516157 A GB3516157 A GB 3516157A GB 3516157 A GB3516157 A GB 3516157A GB 841860 A GB841860 A GB 841860A
Authority
GB
United Kingdom
Prior art keywords
oxide
metal
vessel
iron
plutonium
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
GB3516157A
Inventor
Jack Williams
William James Keith Wright
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 BE572864D priority Critical patent/BE572864A/xx
Priority to NL107464D priority patent/NL107464C/xx
Priority to NL233006D priority patent/NL233006A/xx
Application filed by UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to GB3516157A priority patent/GB841860A/en
Priority to FR1207293D priority patent/FR1207293A/en
Priority to DEU5733A priority patent/DE1135434B/en
Publication of GB841860A publication Critical patent/GB841860A/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
    • C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0213—Obtaining thorium, uranium, or other actinides obtaining uranium by dry processes
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00—Compounds of uranium
    • C01G43/01—Oxides; Hydroxides
    • C01G43/025—Uranium dioxide
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G56/00—Compounds of transuranic elements
    • C01G56/004—Compounds of plutonium
    • C01G56/005—Oxides; Hydroxides
    • 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
    • C22B60/0291—Obtaining thorium, uranium, or other actinides obtaining thorium
    • 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
    • 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
    • G21C19/48—Non-aqueous processes
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00—Physical properties of inorganic compounds
    • C01P2006/10—Solid density
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00—Physical properties of inorganic compounds
    • C01P2006/32—Thermal properties
    • C01P2006/33—Phase transition temperatures
    • C01P2006/34—Melting temperatures
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00—Physical properties of inorganic compounds
    • C01P2006/80—Compositional purity
    • 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

  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Organic Chemistry (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Geology (AREA)
  • Mechanical Engineering (AREA)
  • Materials Engineering (AREA)
  • Manufacturing & Machinery (AREA)
  • Metallurgy (AREA)
  • Environmental & Geological Engineering (AREA)
  • Inorganic Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Manufacture And Refinement Of Metals (AREA)
  • Oxygen, Ozone, And Oxides In General (AREA)
  • Carbon And Carbon Compounds (AREA)

Abstract

841,860. Nuclear fuel processing. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. Nov. 12, 1958 [Nov. 12, 1957], No. 35161/57. Class 39(4). A fissile or fertile oxide is recovered from a dispersion in a metal consisting wholly or predominantly of iron by melting the metal in an inert atmosphere so that the oxide collects on the surface of the molten metal, and separating the oxide mechanically. The metal may be melted in a vessel provided with a spout connected to the bottom of the vessel, so that pure molten metal may be continuously withdrawn, the oxide being removed by vacuum suction. Alternatively the metal may be solidified before separation of the oxide. Oxide of uranium, plutonium, and thorium may be separated from pure iron, cast iron, or mild steel by melting in a graphite vessel in an atmosphere of argon. The Provisional Specification refers to the removal of carbides, silicates, and beryllides of uranium and plutonium, and the range of metals is extended to include aluminium, zirconium and beryllium.
GB3516157A 1957-11-12 1957-11-12 Improvements in or relating to nuclear fuel processing Expired GB841860A (en)

Priority Applications (6)

Application Number Priority Date Filing Date Title
BE572864D BE572864A (en) 1957-11-12
NL107464D NL107464C (en) 1957-11-12
NL233006D NL233006A (en) 1957-11-12
GB3516157A GB841860A (en) 1957-11-12 1957-11-12 Improvements in or relating to nuclear fuel processing
FR1207293D FR1207293A (en) 1957-11-12 1958-11-06 Nuclear fuel processing process
DEU5733A DE1135434B (en) 1957-11-12 1958-11-11 Process for the recovery of an oxide of uranium, plutonium and / or thorium which is present in finely divided form in metallic iron

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB3516157A GB841860A (en) 1957-11-12 1957-11-12 Improvements in or relating to nuclear fuel processing

Publications (1)

Publication Number Publication Date
GB841860A true GB841860A (en) 1960-07-20

Family

ID=10374539

Family Applications (1)

Application Number Title Priority Date Filing Date
GB3516157A Expired GB841860A (en) 1957-11-12 1957-11-12 Improvements in or relating to nuclear fuel processing

Country Status (5)

Country Link
BE (1) BE572864A (en)
DE (1) DE1135434B (en)
FR (1) FR1207293A (en)
GB (1) GB841860A (en)
NL (2) NL233006A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1296137B (en) * 1962-03-08 1969-05-29 Atomic Energy Authority Uk Process for the processing of nuclear fuels

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE102007017715A1 (en) 2007-04-14 2008-10-23 Wr Controls Ab Modular connection system for control cables and methods and joining device for the production
CN112813298A (en) * 2020-12-30 2021-05-18 中核北方核燃料元件有限公司 Method for smelting complex melt

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1296137B (en) * 1962-03-08 1969-05-29 Atomic Energy Authority Uk Process for the processing of nuclear fuels

Also Published As

Publication number Publication date
NL233006A (en) 1900-01-01
FR1207293A (en) 1960-02-16
NL107464C (en) 1900-01-01
BE572864A (en) 1900-01-01
DE1135434B (en) 1962-08-30

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