GB1097597A - Improvements in or relating to the removal of sheaths from nuclear fuel elements - Google Patents

Improvements in or relating to the removal of sheaths from nuclear fuel elements

Info

Publication number
GB1097597A
GB1097597A GB44714/64A GB4471464A GB1097597A GB 1097597 A GB1097597 A GB 1097597A GB 44714/64 A GB44714/64 A GB 44714/64A GB 4471464 A GB4471464 A GB 4471464A GB 1097597 A GB1097597 A GB 1097597A
Authority
GB
United Kingdom
Prior art keywords
sheath
nuclear fuel
removal
sheaths
relating
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
GB44714/64A
Inventor
Piyatilleke Perera Guneratne
William Selwyn Robson
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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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 UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to GB44714/64A priority Critical patent/GB1097597A/en
Publication of GB1097597A publication Critical patent/GB1097597A/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
    • 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

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Perforating, Stamping-Out Or Severing By Means Other Than Cutting (AREA)

Abstract

1,097,597. Removing canning from nuclear fuel. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. Oct. 21, 1965 [Nov. 3, 1964; March 12, 1965], Nos. 44714/64 and 10602/65. Heading G6R. To facilitate removal of the sheath 2 of a fuel element 1 the sheath, having fins 3, is gripped at the ends A, B to enable a high frequency electric current to be passed therethrough whilst it is rotating, the heat generated in the sheath by the H.F. current causing it to expand away from the enclosed fuel member. Rotary ceramic shredders 5, 6 having a helical series of cutting teeth are biased against the rotating sheath and move in the directions M, N whereby the sheath is removed.
GB44714/64A 1964-11-03 1964-11-03 Improvements in or relating to the removal of sheaths from nuclear fuel elements Expired GB1097597A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB44714/64A GB1097597A (en) 1964-11-03 1964-11-03 Improvements in or relating to the removal of sheaths from nuclear fuel elements

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB44714/64A GB1097597A (en) 1964-11-03 1964-11-03 Improvements in or relating to the removal of sheaths from nuclear fuel elements

Publications (1)

Publication Number Publication Date
GB1097597A true GB1097597A (en) 1968-01-03

Family

ID=10434438

Family Applications (1)

Application Number Title Priority Date Filing Date
GB44714/64A Expired GB1097597A (en) 1964-11-03 1964-11-03 Improvements in or relating to the removal of sheaths from nuclear fuel elements

Country Status (1)

Country Link
GB (1) GB1097597A (en)

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2080952A1 (en) * 1970-02-03 1971-11-26 Atomic Energy Authority Uk
DE2753831A1 (en) * 1976-12-13 1978-06-15 Westinghouse Electric Corp PROCEDURE AND EQUIPMENT FOR REMOVING NUCLEAR FUEL TABLETS FROM A METAL FUEL TABLET
US4502642A (en) * 1981-02-05 1985-03-05 Kernforschungsanlage J/u/ lich GmbH Process for the separation of coated nuclear fuel particles from a graphitic matrix and installation for implementing the process
US4514364A (en) * 1982-08-03 1985-04-30 Alkem Gmbh Method for reprocessing a nuclear reactor fuel rod
FR2590068A1 (en) * 1985-11-08 1987-05-15 Novatome METHOD FOR RECYCLING PREVIOUSLY IRRADIATED NUCLEAR FUEL PELLETS IN A FAST NEUTRAL NUCLEAR REACTOR

Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2080952A1 (en) * 1970-02-03 1971-11-26 Atomic Energy Authority Uk
DE2753831A1 (en) * 1976-12-13 1978-06-15 Westinghouse Electric Corp PROCEDURE AND EQUIPMENT FOR REMOVING NUCLEAR FUEL TABLETS FROM A METAL FUEL TABLET
US4502642A (en) * 1981-02-05 1985-03-05 Kernforschungsanlage J/u/ lich GmbH Process for the separation of coated nuclear fuel particles from a graphitic matrix and installation for implementing the process
US4687600A (en) * 1981-02-05 1987-08-18 Kernforschungsanlage Julich Gmbh Process for the separation of coated nuclear fuel particles from a graphitic matrix and installation for implementing the process
US4514364A (en) * 1982-08-03 1985-04-30 Alkem Gmbh Method for reprocessing a nuclear reactor fuel rod
FR2590068A1 (en) * 1985-11-08 1987-05-15 Novatome METHOD FOR RECYCLING PREVIOUSLY IRRADIATED NUCLEAR FUEL PELLETS IN A FAST NEUTRAL NUCLEAR REACTOR
EP0224413A1 (en) * 1985-11-08 1987-06-03 Framatome Process for recycling nuclear fuel pellets previously irradiated in a fast neutrons nuclear reactor
US4803041A (en) * 1985-11-08 1989-02-07 Novatome Process for the recycling of nuclear fuel pellets previously irradiated in a fast neutron nuclear reactor

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