FR2271638A1 - - Google Patents

Info

Publication number
FR2271638A1
FR2271638A1 FR7515226A FR7515226A FR2271638A1 FR 2271638 A1 FR2271638 A1 FR 2271638A1 FR 7515226 A FR7515226 A FR 7515226A FR 7515226 A FR7515226 A FR 7515226A FR 2271638 A1 FR2271638 A1 FR 2271638A1
Authority
FR
France
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.)
Granted
Application number
FR7515226A
Other languages
French (fr)
Other versions
FR2271638B1 (enExample
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.)
HOBEG HOCHTEMPERATURREAKTOR DT
Hobeg Hochtemperaturreaktor Brennelement GmbH
Original Assignee
HOBEG HOCHTEMPERATURREAKTOR DT
Hobeg Hochtemperaturreaktor Brennelement GmbH
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
Priority claimed from DE19742423611 external-priority patent/DE2423611C3/de
Application filed by HOBEG HOCHTEMPERATURREAKTOR DT, Hobeg Hochtemperaturreaktor Brennelement GmbH filed Critical HOBEG HOCHTEMPERATURREAKTOR DT
Publication of FR2271638A1 publication Critical patent/FR2271638A1/fr
Application granted granted Critical
Publication of FR2271638B1 publication Critical patent/FR2271638B1/fr
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
    • G21C19/34—Apparatus or processes for dismantling nuclear fuel, e.g. before reprocessing ; Apparatus or processes for dismantling strings of spent fuel elements
    • G21C19/36—Mechanical means only
    • 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
    • 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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S376/00—Induced nuclear reactions: processes, systems, and elements
    • Y10S376/90—Particular material or material shapes for fission reactors
    • Y10S376/901—Fuel
    • Y10S376/903—Shapes
    • 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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
    • Y10T225/00—Severing by tearing or breaking
    • Y10T225/30—Breaking or tearing apparatus
    • Y10T225/329—Plural breakers

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Solid Fuels And Fuel-Associated Substances (AREA)
FR7515226A 1974-05-15 1975-05-15 Expired FR2271638B1 (enExample)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE19742423611 DE2423611C3 (de) 1974-05-15 Verfahren zur Aufarbeitung blocklörmiger Graphitbrennelemente

Publications (2)

Publication Number Publication Date
FR2271638A1 true FR2271638A1 (enExample) 1975-12-12
FR2271638B1 FR2271638B1 (enExample) 1978-03-17

Family

ID=5915646

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7515226A Expired FR2271638B1 (enExample) 1974-05-15 1975-05-15

Country Status (4)

Country Link
US (1) US4022865A (enExample)
JP (1) JPS50160699A (enExample)
FR (1) FR2271638B1 (enExample)
GB (1) GB1501907A (enExample)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2499295A1 (fr) * 1981-02-05 1982-08-06 Kernforschungsanlage Juelich Procede pour separer d'une matrice graphitique, des particules de matiere combustible nucleaire enrobees, ainsi qu'installation de traitement d'elements combustibles graphitiques de reacteurs nucleaires a haute temperature pour le stade de traitement initial d'une installation de retraitement

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5015437A (en) * 1989-11-17 1991-05-14 Westinghouse Electric Corp. Graphite core blocks for high temperature gas-cooled reactor

Family Cites Families (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US1630759A (en) * 1926-04-23 1927-05-31 Jr Winslow S Pierce Breaking device for hollow cylinders
US2764239A (en) * 1953-03-11 1956-09-25 Marx All Corp Test scoring device
FR1379741A (fr) 1963-10-16 1964-11-27 Electricite De France Procédé de déchemisage et appareil faisant application dudit procédé ou d'un procédé analogue
GB1069277A (en) * 1964-11-16 1967-05-17 Atomic Energy Authority Uk Improvements in or relating to nuclear fuel element fabrication
DE1244143B (de) * 1964-11-21 1967-07-13 Kernforschungsanlage Juelich D Verfahren zur Aufbereitung uranhaltiger Kernbrennstoffe
US3413196A (en) * 1965-09-08 1968-11-26 Atomic Energy Commission Usa Fuel element
FR2028770B1 (enExample) * 1969-01-21 1973-05-25 Snam Progetti
DE1926827A1 (de) * 1969-05-27 1970-12-03 Kernforschungsanlage Juelich Verfahren zum Aufarbeiten von Brenn- und/oder Brutelementen fuer Kernreaktoren
DE1961145C3 (de) * 1969-12-05 1973-10-25 Nukem Gmbh, 6451 Wolfgang Verfahren und Vorrichtungen zur Widergewinnung des Kernbrennstoffes aus Brennelementen graphitmoderierter Hoch temperaturreaktoren
IT958993B (it) * 1972-02-14 1973-10-30 Nukem Gmbh Blocco pressato di combustibile nucleare per reattori di potenza ad alta temperatura e procedimento per la sua fabbricazione

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2499295A1 (fr) * 1981-02-05 1982-08-06 Kernforschungsanlage Juelich Procede pour separer d'une matrice graphitique, des particules de matiere combustible nucleaire enrobees, ainsi qu'installation de traitement d'elements combustibles graphitiques de reacteurs nucleaires a haute temperature pour le stade de traitement initial d'une installation de retraitement

Also Published As

Publication number Publication date
GB1501907A (en) 1978-02-22
FR2271638B1 (enExample) 1978-03-17
DE2423611B2 (de) 1976-03-25
US4022865A (en) 1977-05-10
DE2423611A1 (de) 1975-11-27
JPS50160699A (enExample) 1975-12-26

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Legal Events

Date Code Title Description
ST Notification of lapse