GB879580A - Improvements in or relating to the recovery of uranium - Google Patents

Improvements in or relating to the recovery of uranium

Info

Publication number
GB879580A
GB879580A GB3956558A GB3956558A GB879580A GB 879580 A GB879580 A GB 879580A GB 3956558 A GB3956558 A GB 3956558A GB 3956558 A GB3956558 A GB 3956558A GB 879580 A GB879580 A GB 879580A
Authority
GB
United Kingdom
Prior art keywords
alloy
uranium
coils
heated
whilst
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
GB3956558A
Inventor
Alexander Milne Simpson
Kenneth Hartley
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 GB3956558A priority Critical patent/GB879580A/en
Priority to FR812352A priority patent/FR1242591A/en
Publication of GB879580A publication Critical patent/GB879580A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • 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
    • 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)
  • Chemical & Material Sciences (AREA)
  • Organic Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Geology (AREA)
  • Inorganic Chemistry (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

Uranium is recovered as oxide from a uranium/molybdenum alloy by heating the alloy in an oxidising atmosphere to form and remove molybdenum trioxide leaving a residue of uranium oxide. The oxidation is preferably effected in a current of oxygen at a pressure between 0.2 and 0.5 mm of mercury. The alloy treated, for example containing 9% molybdenum, may have been irradiated in a nuclear reactor and contaminated with fission products. Such an alloy may be heated in a tubular furnace to 1050 DEG C. in a flow of oxygen, whereupon a crystalline sublimate containing molybdenum trioxide forms on the cooler part of the furnace. As shown in the Figures, the alloy is initially contained in a boat 7 in an electrically heated furnace provided with heating coils, 3a, 3b and 3c and with zeolitic molecular <PICT:0879580/III/1> sieves 4. The first two sets of the molecular sieves have a pore size of 13A DEG and the remaining sieves have a pore size of 5A DEG . In operation, the boat 7 is initially heated to 1050 DEG C. whilst oxygen is passed over and when sublimation is complete, the zone surrounded by coil 3a is cooled to 800 DEG C. whilst an inert carrier gas is passed through. The heating zone is then moved forward through coils 3a, 3b, and 3c until the sublimate is moved into the p trap 4. Molybdenum trioxide is retained in the heated part of the trap surrounded by coils 3c whilst fission product metal oxides and some iodine is deposited in the cool unheated portion of the sieve beyond the electric heating coils.
GB3956558A 1958-12-08 1958-12-08 Improvements in or relating to the recovery of uranium Expired GB879580A (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
GB3956558A GB879580A (en) 1958-12-08 1958-12-08 Improvements in or relating to the recovery of uranium
FR812352A FR1242591A (en) 1958-12-08 1959-12-07 Uranium recovery process

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB3956558A GB879580A (en) 1958-12-08 1958-12-08 Improvements in or relating to the recovery of uranium

Publications (1)

Publication Number Publication Date
GB879580A true GB879580A (en) 1961-10-11

Family

ID=10410234

Family Applications (1)

Application Number Title Priority Date Filing Date
GB3956558A Expired GB879580A (en) 1958-12-08 1958-12-08 Improvements in or relating to the recovery of uranium

Country Status (2)

Country Link
FR (1) FR1242591A (en)
GB (1) GB879580A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3666673A (en) * 1969-12-24 1972-05-30 Atomic Energy Commission Method of disposing of radioactive organic waste solutions
FR2750127A1 (en) * 1996-06-21 1997-12-26 Us Energy PURIFICATION OF URANIUM ALLOYS BY DIFFERENTIAL OXIDE SOLUBILITY AND PRODUCTION OF PURIFIED FUEL PRECURSORS
WO2004050207A1 (en) * 2002-12-05 2004-06-17 Technische Universität Darmstadt Sublimation furnace and method that uses the same

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3666673A (en) * 1969-12-24 1972-05-30 Atomic Energy Commission Method of disposing of radioactive organic waste solutions
FR2750127A1 (en) * 1996-06-21 1997-12-26 Us Energy PURIFICATION OF URANIUM ALLOYS BY DIFFERENTIAL OXIDE SOLUBILITY AND PRODUCTION OF PURIFIED FUEL PRECURSORS
WO2004050207A1 (en) * 2002-12-05 2004-06-17 Technische Universität Darmstadt Sublimation furnace and method that uses the same

Also Published As

Publication number Publication date
FR1242591A (en) 1960-09-30

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