GB863571A - Separation of plutonium and fission products from uranium - Google Patents

Separation of plutonium and fission products from uranium

Info

Publication number
GB863571A
GB863571A GB1108246A GB1108246A GB863571A GB 863571 A GB863571 A GB 863571A GB 1108246 A GB1108246 A GB 1108246A GB 1108246 A GB1108246 A GB 1108246A GB 863571 A GB863571 A GB 863571A
Authority
GB
United Kingdom
Prior art keywords
uranium
plutonium
fission products
uranyl
separation
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
GB1108246A
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
Publication of GB863571A publication Critical patent/GB863571A/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
    • C01G56/00—Compounds of transuranic elements
    • C01G56/004—Compounds of plutonium
    • 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
    • C22B60/0286—Obtaining thorium, uranium, or other actinides obtaining uranium refining, melting, remelting, working up uranium
    • 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

Abstract

863,571. Concentration of plutonium. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. April 10, 1946 [April 5, 1945], No. 11082/46. Class 39(4). Plutonium and fission products are separated from neutron-irradiated uranium by forming a solution in which the uranium is present in the uranyl form and crystallising out a uranium salt, leaving plutonium and fission products in the mother liquor. Neutronirradiated uranium may be dissolved in concentrated nitric acid or sulphuric acid at 75‹- 100‹C., the hot solution cooled with agitation to 25-30‹C., and the crystals centrifuged off; for separation of more plutonium, the crystals are redissolved and the process repeated. Alternatively an acidic saturated solution of the uranium may be formed and then nitrogen dioxide gas, concentrated nitric acid, sulphur trioxide gas, or fuming sulphuric acid added to effect crystallisation. Reference is also made to the crystallisation of uranyl phosphate and uranyl oxilate.
GB1108246A 1945-04-05 1946-04-10 Separation of plutonium and fission products from uranium Expired GB863571A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US863571XA 1945-04-05 1945-04-05

Publications (1)

Publication Number Publication Date
GB863571A true GB863571A (en) 1961-03-22

Family

ID=22198059

Family Applications (1)

Application Number Title Priority Date Filing Date
GB1108246A Expired GB863571A (en) 1945-04-05 1946-04-10 Separation of plutonium and fission products from uranium

Country Status (1)

Country Link
GB (1) GB863571A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP1329906A2 (en) * 2002-01-17 2003-07-23 Japan Nuclear Cycle Development Institute Process for reprocessing spent nuclear fuels by utilizing phenomenon of cocrystallization

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP1329906A2 (en) * 2002-01-17 2003-07-23 Japan Nuclear Cycle Development Institute Process for reprocessing spent nuclear fuels by utilizing phenomenon of cocrystallization
EP1329906A3 (en) * 2002-01-17 2005-01-12 Japan Nuclear Cycle Development Institute Process for reprocessing spent nuclear fuels by utilizing phenomenon of cocrystallization
US7011798B2 (en) 2002-01-17 2006-03-14 Japan Nuclear Cycle Development Institute Process for reprocessing spent nuclear fuels by utilizing phenomenon of cocrystallization

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