ES357826A1 - A method of dissolving plutonium-aluminium alloys - Google Patents

A method of dissolving plutonium-aluminium alloys

Info

Publication number
ES357826A1
ES357826A1 ES357826A ES357826A ES357826A1 ES 357826 A1 ES357826 A1 ES 357826A1 ES 357826 A ES357826 A ES 357826A ES 357826 A ES357826 A ES 357826A ES 357826 A1 ES357826 A1 ES 357826A1
Authority
ES
Spain
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
ES357826A
Other languages
Spanish (es)
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 ES357826A1 publication Critical patent/ES357826A1/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

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.
ES357826A 1967-09-04 1968-09-04 A method of dissolving plutonium-aluminium alloys Expired ES357826A1 (en)

Applications Claiming Priority (1)

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

Publications (1)

Publication Number Publication Date
ES357826A1 true ES357826A1 (en) 1970-07-01

Family

ID=8637734

Family Applications (1)

Application Number Title Priority Date Filing Date
ES357826A Expired ES357826A1 (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)

Families Citing this family (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
GB1213504A (en) 1970-11-25
BE719409A (en) 1969-01-16

Similar Documents

Publication Publication Date Title
GB835266A (en) Improvements relating to nuclear reactors
DK136558B (en) Method for increasing the circulation of the coolant in a pressure vessel of an atomic core reactor with natural circulation of the coolant in the pressure vessel using a jet pump.
GB1106547A (en) Method and apparatus for the electrolytic de-silvering of photographic processing liquids
ES357826A1 (en) A method of dissolving plutonium-aluminium alloys
GB856946A (en) Improvements in or relating to fast breeder reactors
GB1068104A (en) Dissolution of nuclear fuel
GB1311045A (en) Closed fluid system pressurization
JPS6447976A (en) Tester for private generator or the like
GB1281669A (en) Process and apparatus for the storage of nuclear irradiated fuel elements
GB1333542A (en) Laser energized plasma source
GB953724A (en) Apparatus for intensifying light
FR2085603A1 (en) Processing of nuclear fuel rods
GB1335509A (en) Method for the treatment of irradiated nuclear fuel elements
ES335922A1 (en) Spectral shift reactor control
GB1100767A (en) Improvements in and relating to nuclear reactors
ES415449A1 (en) Nuclear reactor including emergency cooling system
BE594471A (en) Device for the direct supply of electrical energy from nuclear processes that occur in reactors.
ES369931A1 (en) Process for the recovery of fissile materials from chemical decanning solutions
ES314799A1 (en) Procedure for the use of new uranium alloys in nuclear fuels. (Machine-translation by Google Translate, not legally binding)
GB1302777A (en)
GB1015526A (en) Apparatus for the regeneration of an ion exchanger
Petrov et al. Use of a laser for spectral-isotopic determination of volumetric and surface content of oxygen in metals(Isotope exchange of C (O-18) and C (O-16) 2 with O dissolved in metal for volumetric and surface analysis)
GB966004A (en) Method of dissolving plutonium
GB1086505A (en) A method of and apparatus for treating a liquid by ion exchangers
GB874854A (en) Plutonium-cerium-cobalt, plutonium-cerium-nickel and plutonium-cerium-nickel-cobalt alloys