BE762373A - Traitement d'elements combustibles nucleaires - Google Patents

Traitement d'elements combustibles nucleaires

Info

Publication number
BE762373A
BE762373A BE762373A BE762373A BE762373A BE 762373 A BE762373 A BE 762373A BE 762373 A BE762373 A BE 762373A BE 762373 A BE762373 A BE 762373A BE 762373 A BE762373 A BE 762373A
Authority
BE
Belgium
Prior art keywords
treatment
nuclear fuel
fuel elements
elements
nuclear
Prior art date
Application number
BE762373A
Other languages
English (en)
French (fr)
Original Assignee
Atomic Energy Authority Uk
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 Atomic Energy Authority Uk filed Critical Atomic Energy Authority Uk
Publication of BE762373A publication Critical patent/BE762373A/xx

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
    • G21C19/34—Apparatus or processes for dismantling nuclear fuel, e.g. before reprocessing ; Apparatus or processes for dismantling strings of spent fuel elements
    • 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

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Solid Fuels And Fuel-Associated Substances (AREA)
BE762373A 1970-02-03 1971-02-01 Traitement d'elements combustibles nucleaires BE762373A (fr)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB5227/70A GB1274357A (en) 1970-02-03 1970-02-03 Improvements in or relating to the treatment of irradiated nuclear fuel elements

Publications (1)

Publication Number Publication Date
BE762373A true BE762373A (fr) 1971-08-02

Family

ID=9792115

Family Applications (1)

Application Number Title Priority Date Filing Date
BE762373A BE762373A (fr) 1970-02-03 1971-02-01 Traitement d'elements combustibles nucleaires

Country Status (5)

Country Link
BE (1) BE762373A (OSRAM)
CA (1) CA918246A (OSRAM)
DE (1) DE2104350A1 (OSRAM)
FR (1) FR2080952B1 (OSRAM)
GB (1) GB1274357A (OSRAM)

Families Citing this family (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3228979A1 (de) * 1982-08-03 1984-02-09 Alkem Gmbh, 6450 Hanau Verfahren zum aufarbeiten eines kernreaktorbrennstabes
FR2590068B1 (fr) * 1985-11-08 1987-12-11 Novatome Procede de recyclage de pastilles de combustible nucleaire precedemment irradiees dans un reacteur nucleaire a neutrons rapides
FR2667533A1 (fr) * 1990-10-05 1992-04-10 Commissariat Energie Atomique Procede pour decouper un tube metallique par induction et application a la separation des combustibles irradies de leur gaine metallique.
FR2710181B1 (fr) * 1993-09-13 1995-11-03 Cogema Procédé et dispositif de découpe par induction d'éléments d'une installation nucléaire.
RU2194783C1 (ru) * 2001-04-13 2002-12-20 Государственное унитарное предприятие "Всероссийский научно-исследовательский институт химической технологии" Способ извлечения керамического ядерного топлива из тепловыделяющих элементов и тепловыделяющих сборок
RU2200766C2 (ru) * 2001-04-19 2003-03-20 Государственное унитарное предприятие "Всероссийский научно-исследовательский институт химической технологии" Способ извлечения керамического ядерного топлива из пакетов тепловыделяющих элементов

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1097597A (en) * 1964-11-03 1968-01-03 Atomic Energy Authority Uk Improvements in or relating to the removal of sheaths from nuclear fuel elements
DE1589815A1 (de) * 1967-03-03 1970-05-14 Kernforschung Gmbh Ges Fuer Verfahren und Vorrichtung zum Durchtrennen von Reaktorbrennelementhuellen,Bestrahlungskapseln oder Lager- und Transportbehaeltern mittels Hochfrequenz
DE1589850A1 (de) * 1967-03-03 1970-09-17 Kernforschung Gmbh Ges Fuer Verfahren und Vorrichtung zum Auftrennen von Reaktorbrennelementhuellen,Bestrahlungskapseln u. dgl.

Also Published As

Publication number Publication date
FR2080952B1 (OSRAM) 1975-01-17
CA918246A (en) 1973-01-02
DE2104350A1 (de) 1971-08-19
GB1274357A (en) 1972-05-17
FR2080952A1 (OSRAM) 1971-11-26

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