BE861797A - Procede et appareil pour la recuperation de comprimes de combustible au depart d'elements combustibles nucleaires - Google Patents

Procede et appareil pour la recuperation de comprimes de combustible au depart d'elements combustibles nucleaires

Info

Publication number
BE861797A
BE861797A BE183410A BE183410A BE861797A BE 861797 A BE861797 A BE 861797A BE 183410 A BE183410 A BE 183410A BE 183410 A BE183410 A BE 183410A BE 861797 A BE861797 A BE 861797A
Authority
BE
Belgium
Prior art keywords
tablets
nuclear fuel
fuel elements
recovering combustible
combustible
Prior art date
Application number
BE183410A
Other languages
English (en)
Original Assignee
Westinghouse Electric Corp
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 Westinghouse Electric Corp filed Critical Westinghouse Electric Corp
Publication of BE861797A publication Critical patent/BE861797A/fr

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
    • 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
    • Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
    • Y10T29/00—Metal working
    • Y10T29/49—Method of mechanical manufacture
    • Y10T29/49815—Disassembling
    • Y10T29/49822—Disassembling by applying force
    • Y10T29/49824—Disassembling by applying force to elastically deform work part or connector

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)
  • Manufacture And Refinement Of Metals (AREA)
  • Solid Fuels And Fuel-Associated Substances (AREA)
BE183410A 1976-12-13 1977-12-13 Procede et appareil pour la recuperation de comprimes de combustible au depart d'elements combustibles nucleaires BE861797A (fr)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US05/749,869 US4116767A (en) 1976-12-13 1976-12-13 Fluid pressure apparatus for recovering fuel pellets from nuclear fuel elements

Publications (1)

Publication Number Publication Date
BE861797A true BE861797A (fr) 1978-06-13

Family

ID=25015561

Family Applications (1)

Application Number Title Priority Date Filing Date
BE183410A BE861797A (fr) 1976-12-13 1977-12-13 Procede et appareil pour la recuperation de comprimes de combustible au depart d'elements combustibles nucleaires

Country Status (10)

Country Link
US (1) US4116767A (fr)
JP (1) JPS5374700A (fr)
BE (1) BE861797A (fr)
CA (1) CA1065589A (fr)
DE (1) DE2753831C2 (fr)
ES (1) ES464983A1 (fr)
FR (1) FR2373859A1 (fr)
GB (1) GB1539308A (fr)
IT (1) IT1090148B (fr)
SE (1) SE424781B (fr)

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4312708A (en) * 1979-03-05 1982-01-26 Thaxton, Inc. Reactor stud hole plug unit
DE3228979A1 (de) * 1982-08-03 1984-02-09 Alkem Gmbh, 6450 Hanau Verfahren zum aufarbeiten eines kernreaktorbrennstabes
DE3409707A1 (de) * 1984-03-16 1985-09-19 Kernforschungsanlage Jülich GmbH, 5170 Jülich Verfahren und vorrichtung zum abtrennen von keramischen kernbrennstoffen von metallischen huell- oder traegerkoerpern
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
CN112037950B (zh) * 2020-09-24 2022-02-11 中国核动力研究设计院 一种燃料棒裂变产物释放模拟装置及其使用方法

Family Cites Families (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2827405A (en) * 1956-05-09 1958-03-18 Ca Atomic Energy Ltd Method of desheathing of uranium fuel rods
GB912537A (en) * 1959-11-26 1962-12-12 Atomic Energy Authority Uk Improvements in or relating to nuclear reactor refuelling machines
US3293734A (en) * 1963-12-13 1966-12-27 Fairey Eng Machines for removing splitter blades from nuclear reactor fuel cans
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
FR1452479A (fr) * 1965-11-02 1966-02-25 Atomic Energy Authority Uk Procédé pour enlever les gaines des cartouches de combustible nucléaire irradiées
US3914848A (en) * 1972-03-01 1975-10-28 Caterpillar Tractor Co Method for reclaiming collet hose fittings
DE2246180A1 (de) * 1972-09-20 1974-04-11 Hobeg Hochtemperaturreaktor Brennelemente fuer hochtemperaturreaktoren mit besonderer eignung fuer die wiederverwendung des strukturgraphits
DE2344266C3 (de) * 1973-09-01 1983-02-24 Fried. Krupp Gmbh, 4300 Essen Greifvorrichtung, insbesondere für Steuer- und Abschaltstäbe in einem Kernreaktor
US3990591A (en) * 1975-01-31 1976-11-09 Stearns-Roger Corporation Multiple function nuclear handling apparatus

Also Published As

Publication number Publication date
FR2373859A1 (fr) 1978-07-07
US4116767A (en) 1978-09-26
SE7714148L (sv) 1978-06-14
CA1065589A (fr) 1979-11-06
DE2753831A1 (de) 1978-06-15
ES464983A1 (es) 1980-12-01
JPS5374700A (en) 1978-07-03
JPS578437B2 (fr) 1982-02-16
IT1090148B (it) 1985-06-18
GB1539308A (en) 1979-01-31
SE424781B (sv) 1982-08-09
DE2753831C2 (de) 1986-11-20

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Legal Events

Date Code Title Description
RE Patent lapsed

Owner name: WESTINGHOUSE ELECTRIC CORP.

Effective date: 19891231