GB1501907A - Working up block form graphite nuclear fuel elements - Google Patents

Working up block form graphite nuclear fuel elements

Info

Publication number
GB1501907A
GB1501907A GB1895475A GB1895475A GB1501907A GB 1501907 A GB1501907 A GB 1501907A GB 1895475 A GB1895475 A GB 1895475A GB 1895475 A GB1895475 A GB 1895475A GB 1501907 A GB1501907 A GB 1501907A
Authority
GB
United Kingdom
Prior art keywords
nuclear fuel
pieces
fuel elements
working
block form
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
GB1895475A
Other languages
English (en)
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 GmbH
Original Assignee
HOBEG 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 GmbH filed Critical HOBEG GmbH
Publication of GB1501907A publication Critical patent/GB1501907A/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
    • G21C19/34—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)
GB1895475A 1974-05-15 1975-05-06 Working up block form graphite nuclear fuel elements Expired GB1501907A (en)

Applications Claiming Priority (1)

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

Publications (1)

Publication Number Publication Date
GB1501907A true GB1501907A (en) 1978-02-22

Family

ID=5915646

Family Applications (1)

Application Number Title Priority Date Filing Date
GB1895475A Expired GB1501907A (en) 1974-05-15 1975-05-06 Working up block form graphite nuclear fuel elements

Country Status (4)

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

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3103900C2 (de) * 1981-02-05 1984-02-02 Kernforschungsanlage Jülich GmbH, 5170 Jülich Anlage zum Aufbereiten graphitischer Brennelemente von Hochtemperatur-Kernreaktoren
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

Also Published As

Publication number Publication date
DE2423611A1 (de) 1975-11-27
FR2271638A1 (enExample) 1975-12-12
FR2271638B1 (enExample) 1978-03-17
US4022865A (en) 1977-05-10
JPS50160699A (enExample) 1975-12-26
DE2423611B2 (de) 1976-03-25

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Legal Events

Date Code Title Description
PS Patent sealed [section 19, patents act 1949]
PCNP Patent ceased through non-payment of renewal fee