GB1213504A - A method of dissolving plutonium-aluminium alloys - Google Patents

A method of dissolving plutonium-aluminium alloys

Info

Publication number
GB1213504A
GB1213504A GB4199568A GB4199568A GB1213504A GB 1213504 A GB1213504 A GB 1213504A GB 4199568 A GB4199568 A GB 4199568A GB 4199568 A GB4199568 A GB 4199568A GB 1213504 A GB1213504 A GB 1213504A
Authority
GB
United Kingdom
Prior art keywords
plutonium
solution
vessels
hydroxide
vessel
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
GB4199568A
Inventor
Michel Ganivet
Jean Girard
Jean-Marie Meniere
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 GB1213504A publication Critical patent/GB1213504A/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
    • 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)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

1,213,504. Processing nuclear fuel. COMMISSARIAT A L'ENERGIE ATOMIQUE. 4 Sept., 1968 [4 Sept., 1967], No. 41995/68. Heading G6R. [Also in Division B1] Apparatus for dissolving plutonium - aluminium alloy comprises a vessel 4 where the alloy is treated with potassium hydroxide solution to form a solution of potassium aluminate and a precipitate of plutonium hydroxide, and a second vessel 10 containing a replaceable filter element 14 which separates the plutonium hydroxide precipitate from the potassium aluminate solution which flows through to storage vessel 22; the plutonium hydroxide is dissolved in nitric acid and the solution stored in vessels 20, 21. Heaters 5, 12 supply heat to vessels 4, 10 and cause circulation of liquid through these vessels. The apparatus is surrounded by a glove box.
GB4199568A 1967-09-04 1968-09-04 A method of dissolving plutonium-aluminium alloys Expired GB1213504A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR119883 1967-09-04

Publications (1)

Publication Number Publication Date
GB1213504A true GB1213504A (en) 1970-11-25

Family

ID=8637734

Family Applications (1)

Application Number Title Priority Date Filing Date
GB4199568A Expired GB1213504A (en) 1967-09-04 1968-09-04 A method of dissolving plutonium-aluminium alloys

Country Status (5)

Country Link
BE (1) BE719409A (en)
ES (1) ES357826A1 (en)
FR (1) FR1550190A (en)
GB (1) GB1213504A (en)
LU (1) LU56776A1 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2508010A (en) * 2012-11-19 2014-05-21 Bradtec Decon Technologies Ltd Treatment of Radioactive Material

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2508010A (en) * 2012-11-19 2014-05-21 Bradtec Decon Technologies Ltd Treatment of Radioactive Material

Also Published As

Publication number Publication date
FR1550190A (en) 1968-12-20
LU56776A1 (en) 1968-11-22
ES357826A1 (en) 1970-07-01
BE719409A (en) 1969-01-16

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Legal Events

Date Code Title Description
CSNS Application of which complete specification have been accepted and published, but patent is not sealed