CH370492A - Process for separating a rod of irradiated nuclear fuel from its cladding and device for carrying out the process - Google Patents

Process for separating a rod of irradiated nuclear fuel from its cladding and device for carrying out the process

Info

Publication number
CH370492A
CH370492A CH657961A CH657961A CH370492A CH 370492 A CH370492 A CH 370492A CH 657961 A CH657961 A CH 657961A CH 657961 A CH657961 A CH 657961A CH 370492 A CH370492 A CH 370492A
Authority
CH
Switzerland
Prior art keywords
cladding
separating
carrying
rod
nuclear fuel
Prior art date
Application number
CH657961A
Other languages
French (fr)
Inventor
Dabernard Pierre
Guilloteau Rene
Original Assignee
Commissariat Energie Atomique
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 Commissariat Energie Atomique filed Critical Commissariat Energie Atomique
Publication of CH370492A publication Critical patent/CH370492A/en

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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S83/00—Cutting
    • Y10S83/924—Work wrapped or coated around a core, not part of the machine
    • 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
    • Y10S83/00—Cutting
    • Y10S83/929—Particular nature of work or product
    • Y10S83/93—Radioactive
    • 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
    • Y10T83/00—Cutting
    • Y10T83/04—Processes
    • Y10T83/0596—Cutting wall of hollow work
    • 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
    • Y10T83/00—Cutting
    • Y10T83/202—With product handling means
    • Y10T83/2074—Including means to divert one portion of product from another
    • 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
    • Y10T83/00—Cutting
    • Y10T83/768—Rotatable disc tool pair or tool and carrier
    • Y10T83/7755—Carrier for rotatable tool movable during cutting
    • Y10T83/7763—Tool carrier reciprocable rectilinearly
    • Y10T83/7776—With means to reciprocate carrier

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)
  • Processing Of Solid Wastes (AREA)
  • Processing And Handling Of Plastics And Other Materials For Molding In General (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)
CH657961A 1960-06-13 1961-06-06 Process for separating a rod of irradiated nuclear fuel from its cladding and device for carrying out the process CH370492A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR829816A FR1267862A (en) 1960-06-13 1960-06-13 Machine for extruding bars of irradiated material contained in metal sheaths

Publications (1)

Publication Number Publication Date
CH370492A true CH370492A (en) 1963-07-15

Family

ID=8733271

Family Applications (1)

Application Number Title Priority Date Filing Date
CH657961A CH370492A (en) 1960-06-13 1961-06-06 Process for separating a rod of irradiated nuclear fuel from its cladding and device for carrying out the process

Country Status (8)

Country Link
US (1) US3173320A (en)
BE (1) BE604631A (en)
CH (1) CH370492A (en)
DE (1) DE1280427B (en)
FR (1) FR1267862A (en)
GB (1) GB934622A (en)
LU (1) LU40234A1 (en)
NL (1) NL265865A (en)

Families Citing this family (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3563121A (en) * 1968-12-09 1971-02-16 Deering Milliken Res Corp Cutting apparatus
DE1904288A1 (en) * 1969-01-29 1970-08-13 Glanzstoff Ag Device for cutting threads wound on bobbins into staple fibers
DE2420577C2 (en) * 1973-05-14 1982-12-02 Westinghouse Electric Corp., 15222 Pittsburgh, Pa. Method and apparatus for removing nuclear fuel from jacketed nuclear fuel assemblies
US4295401A (en) * 1976-07-29 1981-10-20 Nus Corporation Apparatus for disposing of radioactive fuel channels
FR2472250A1 (en) * 1979-12-20 1981-06-26 Nukem Gmbh METHOD AND APPARATUS FOR EXTINGUISHING NUCLEAR COMBUSTIBLE MATERIALS FROM THEIR SOLDERING TUBES
GB2165688B (en) * 1984-08-21 1988-06-22 Atomic Energy Authority Uk Dismantling irradiated nuclear fuel elements
US5276965A (en) * 1992-02-13 1994-01-11 The Atlantic Group, Inc. Method for dismantling potentially contaminated tubes from a tube bundle
KR100693329B1 (en) * 2005-10-26 2007-03-09 한국원자력연구소 Separation and receiving device for spent nuclear fuel rods
FR3001572B1 (en) * 2013-01-25 2015-02-27 Technicatome INTEGRATED TYPE PRESSURE WATER NUCLEAR REACTOR COMPRISING AN INTEGRATED PRESSURIZER.
CN109859869B (en) * 2019-03-11 2022-03-25 中国核动力研究设计院 Irradiation device suitable for single fuel element transient test

Family Cites Families (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US429292A (en) * 1890-06-03 Machine for stripping the lead covering from conductors
US1366082A (en) * 1918-12-24 1921-01-18 Burgess Battery Co Recovering components of exhausted dry-battery cells
GB430412A (en) * 1933-10-19 1935-06-19 Charles Percy Seckham Improved apparatus for stripping electric cables
US2046341A (en) * 1935-03-16 1936-07-07 Okonite Callender Cable Co Inc Method of and apparatus for removing sheaths from cables and the like
US2209209A (en) * 1938-12-12 1940-07-23 Charles H Ruby Method of dismantling containers
US2880636A (en) * 1947-03-04 1959-04-07 Freedman Melvin Cutting and wedging jacket remover
US2827405A (en) * 1956-05-09 1958-03-18 Ca Atomic Energy Ltd Method of desheathing of uranium fuel rods

Also Published As

Publication number Publication date
DE1280427B (en) 1968-10-17
NL265865A (en) 1900-01-01
GB934622A (en) 1963-08-21
US3173320A (en) 1965-03-16
BE604631A (en) 1961-10-02
FR1267862A (en) 1961-07-28
LU40234A1 (en) 1961-08-07

Similar Documents

Publication Publication Date Title
FR1446362A (en) Method and device for the evacuation of gaseous fission products from the fuel elements of nuclear reactors
FR1230149A (en) Device and method for confining a plasma
FR1220414A (en) nuclear reactor fuel element, method and apparatus for its manufacture
CH370492A (en) Process for separating a rod of irradiated nuclear fuel from its cladding and device for carrying out the process
FR1343107A (en) Apparatus and method for determining the combustion quality of a fuel
CH505443A (en) Process for recovering the constituents of irradiated nuclear fuel and device for carrying out the process
FR1506677A (en) Method and apparatus for determining the aging of nuclear fuel from a reactor
CH375802A (en) Tube for sealingly passing through a nuclear reactor core and method for manufacturing this tube
FR1181175A (en) Apparatus for handling nuclear reactor fuel elements
CH379826A (en) Plant irradiation process and device for its implementation
CH373507A (en) Method of combustion of a fluid fuel and apparatus for its implementation
FR1234694A (en) Equipment for detecting cracks in fuel cartridges for nuclear reactors
CH388476A (en) Method for manufacturing a nuclear fuel rod, fuel rod manufactured according to this method and device for implementing the method
FR1218526A (en) Cladding for fuel rods of a heavy water nuclear reactor
FR1143942A (en) Process and equipment for the development of waste fuels and lean fuels
FR1274265A (en) Process for the operation of a nuclear reactor and reactor for its implementation
BE576247A (en) Method and apparatus for determining the condition of a nuclear reactor
FR1222070A (en) Method and means for the electrolytic purification of plutonium
FR1255566A (en) Refining process and device for its implementation
BE611227A (en) Method and apparatus for sampling a gas stream, in particular a scrub gas stream in nuclear reactors
FR1193128A (en) Method and device for spacing pipes
FR1272206A (en) Method and apparatus for studying explosions by a stereoscopic process
FR1225613A (en) Process for the enrichment and use of nuclear fuels
BE600215A (en) Production of gas from fuels and device for carrying out the related process
CH403137A (en) Method of combustion of a fuel and apparatus for its implementation