JPS6472098A - Apparatus used for work of dismantling nuclear fuel subassembly - Google Patents

Apparatus used for work of dismantling nuclear fuel subassembly

Info

Publication number
JPS6472098A
JPS6472098A JP19592788A JP19592788A JPS6472098A JP S6472098 A JPS6472098 A JP S6472098A JP 19592788 A JP19592788 A JP 19592788A JP 19592788 A JP19592788 A JP 19592788A JP S6472098 A JPS6472098 A JP S6472098A
Authority
JP
Japan
Prior art keywords
fuel
cylinder
assembly
subassembly
axial direction
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.)
Granted
Application number
JP19592788A
Other languages
Japanese (ja)
Other versions
JP2643994B2 (en
Inventor
Toomasu Kenedeii Suteiibun
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.)
Sellafield Ltd
Original Assignee
British Nuclear Fuels PLC
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 British Nuclear Fuels PLC filed Critical British Nuclear Fuels PLC
Publication of JPS6472098A publication Critical patent/JPS6472098A/en
Application granted granted Critical
Publication of JP2643994B2 publication Critical patent/JP2643994B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/34Apparatus or processes for dismantling nuclear fuel, e.g. before reprocessing ; Apparatus or processes for dismantling strings of spent fuel elements
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02WCLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00Technologies for solid waste management
    • Y02W30/50Reuse, 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)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Automatic Assembly (AREA)

Abstract

PURPOSE: To easily carry out the disassembling work of an irradiated subassembly by pulling out a fuel pin by moving a carrying body mounted with a fuel pin locking device in the axial direction of a fuel subassembly supporting body or in a plane crossing the axial direction. CONSTITUTION: Both ends of a cylinder 20 are connected to a rear table 24 and a side slipping table 26 with universal joints 22 and the cylinder 20 is moved in a plane parallel to the exposed end 13 of a fuel element 12 by means of a step motor 28 and a lead screw 30. Since a chuck assembly 32 connected to a carrying body 18 is mounted on a fuel pin coupling device 16 by means of a cylinder 34, the movement of the assembly 32 in the axial direction is performed by means of the cylinders 20 and 34. The device 16 is matched with a positioning socket 38 by driving the device 16 by means of the cylinders 20 and 34 and further driven to a pin pulling position by means of the motor 28. At the pulling position, a nuclear fuel subassembly can be disassembled easily, by moving the assembly 32 forward by energizing the cylinder 34 and engaging the assembly 34 with the fuel pin.
JP19592788A 1987-08-06 1988-08-05 Apparatus for dismantling nuclear fuel subassemblies Expired - Lifetime JP2643994B2 (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
GB8718645A GB8718645D0 (en) 1987-08-06 1987-08-06 Dismantling of nuclear fuel sub-assemblies
GB8718645 1987-08-06

Publications (2)

Publication Number Publication Date
JPS6472098A true JPS6472098A (en) 1989-03-16
JP2643994B2 JP2643994B2 (en) 1997-08-25

Family

ID=10621919

Family Applications (1)

Application Number Title Priority Date Filing Date
JP19592788A Expired - Lifetime JP2643994B2 (en) 1987-08-06 1988-08-05 Apparatus for dismantling nuclear fuel subassemblies

Country Status (4)

Country Link
JP (1) JP2643994B2 (en)
DE (1) DE3826316C2 (en)
FR (1) FR2619243B1 (en)
GB (2) GB8718645D0 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2010237206A (en) * 2009-03-30 2010-10-21 Ge-Hitachi Nuclear Energy Americas Llc System for assembling or disassembling segmental rod

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3827579A (en) * 1968-03-25 1974-08-06 Gen Electric Irradiated fuel processing system
US4174369A (en) * 1976-12-13 1979-11-13 Westinghouse Electric Corp. Fluid pressure method for recovering fuel pellets from nuclear fuel elements
US4192715A (en) * 1977-08-23 1980-03-11 Batjukov Vladimir I Fuel assembly handling system of nuclear reactor
US4446098A (en) * 1981-05-29 1984-05-01 Westinghouse Electric Corp. Spent fuel consolidation system
FR2534732A1 (en) * 1982-10-13 1984-04-20 Cerca Process and device for dismantling irradiated rod clusters.
DE3530410A1 (en) * 1985-08-26 1987-03-05 Steag Kernenergie Gmbh Method for compressing spent fuel elements and an arrangement for carrying out the method

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2010237206A (en) * 2009-03-30 2010-10-21 Ge-Hitachi Nuclear Energy Americas Llc System for assembling or disassembling segmental rod

Also Published As

Publication number Publication date
GB8718645D0 (en) 1987-10-07
JP2643994B2 (en) 1997-08-25
GB2207798B (en) 1990-03-14
FR2619243B1 (en) 1990-03-02
DE3826316A1 (en) 1989-02-16
FR2619243A1 (en) 1989-02-10
GB2207798A (en) 1989-02-08
DE3826316C2 (en) 1996-08-14
GB8817165D0 (en) 1988-08-24

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