GB1170385A - An Apparatus for Dissolving Uranium-Aluminium Alloys - Google Patents

An Apparatus for Dissolving Uranium-Aluminium Alloys

Info

Publication number
GB1170385A
GB1170385A GB3727168A GB3727168A GB1170385A GB 1170385 A GB1170385 A GB 1170385A GB 3727168 A GB3727168 A GB 3727168A GB 3727168 A GB3727168 A GB 3727168A GB 1170385 A GB1170385 A GB 1170385A
Authority
GB
United Kingdom
Prior art keywords
uranium
aug
liquid
aluminium alloys
alloy
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
GB3727168A
Inventor
Andre Delpech
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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
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 Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Publication of GB1170385A publication Critical patent/GB1170385A/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
    • 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
    • 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

1,170,385. Liquid/solid contact apparatus. COMMISSARIAT A L'ENERGIE ATOMIQUE. 5 Aug., 1968 [9 Aug., 1967], No. 37271/68. Heading B1F. Uranium aluminium alloy from 3 is reacted with NaOH from 2 in chamber 1, grid 5 holds back particles of alloy, and grids 13, 13' burst any bubbles in the hydrogen gas leaving through 12. Any liquid in 12 and condensed vapours from condenser 17 are recycled via 14. Uranium oxides are withdrawn via 7. Electric probe 20 acts as a safety device controlling electromagnetic discharge valve 19 and proportioning pump 2. Washing water may be introduced through inlet 22.
GB3727168A 1967-08-09 1968-08-05 An Apparatus for Dissolving Uranium-Aluminium Alloys Expired GB1170385A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR117457A FR1539924A (en) 1967-08-09 1967-08-09 Device for dissolving uranium-aluminum alloys

Publications (1)

Publication Number Publication Date
GB1170385A true GB1170385A (en) 1969-11-12

Family

ID=8636669

Family Applications (1)

Application Number Title Priority Date Filing Date
GB3727168A Expired GB1170385A (en) 1967-08-09 1968-08-05 An Apparatus for Dissolving Uranium-Aluminium Alloys

Country Status (6)

Country Link
BE (1) BE718423A (en)
CH (1) CH494822A (en)
ES (1) ES357035A1 (en)
FR (1) FR1539924A (en)
GB (1) GB1170385A (en)
LU (1) LU56628A1 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2306592A1 (en) * 1973-02-10 1974-08-15 Kernforschung Gmbh Ges Fuer PLANT FOR DIGESTING AND PROCESSING ACTINIDES-ALUMINUM ALLOYS OR CERMETS CONTAINING ALUMINUM

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2645329B1 (en) * 1989-03-30 1991-05-31 Commissariat Energie Atomique PARTS DISCHARGE CHANNEL EQUIPPED WITH AN AERAULIC BARRIER AND APPLICATION TO A PROCESSING KIT FOR IRRADIATED COMBUSTIBLE ELEMENTS

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2306592A1 (en) * 1973-02-10 1974-08-15 Kernforschung Gmbh Ges Fuer PLANT FOR DIGESTING AND PROCESSING ACTINIDES-ALUMINUM ALLOYS OR CERMETS CONTAINING ALUMINUM

Also Published As

Publication number Publication date
LU56628A1 (en) 1968-11-14
BE718423A (en) 1968-12-31
ES357035A1 (en) 1970-09-01
FR1539924A (en) 1968-09-20
CH494822A (en) 1970-08-15

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