GB1176565A - Dismantling Fuel Element Strings for Nuclear Reactors - Google Patents

Dismantling Fuel Element Strings for Nuclear Reactors

Info

Publication number
GB1176565A
GB1176565A GB25387/67A GB2538767A GB1176565A GB 1176565 A GB1176565 A GB 1176565A GB 25387/67 A GB25387/67 A GB 25387/67A GB 2538767 A GB2538767 A GB 2538767A GB 1176565 A GB1176565 A GB 1176565A
Authority
GB
United Kingdom
Prior art keywords
bar
tube
plug
string
puller
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
GB25387/67A
Inventor
Reginald Kenneth Cook
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.)
NUCLEAR DESIGN AND CONSTRUCTIO
Original Assignee
NUCLEAR DESIGN AND CONSTRUCTIO
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 NUCLEAR DESIGN AND CONSTRUCTIO filed Critical NUCLEAR DESIGN AND CONSTRUCTIO
Priority to GB25387/67A priority Critical patent/GB1176565A/en
Publication of GB1176565A publication Critical patent/GB1176565A/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
    • G21C19/02—Details of handling arrangements
    • 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
    • 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)
  • Working Measures On Existing Buildindgs (AREA)

Abstract

1,176,565. Breaking metals. NUCLEAR DESIGN & CONSTRUCTION (1966) Ltd. 30 May, 1968 [1 June, 1967], No. 25387/67. Heading B3E. [Also in Division G6] Apparatus for dismantling a spent fuel element string 14 consisting of a number of fuel elements mounted on a tie bar 15 connected to a standpipe shield plug 16, includes means for applying intense heat to a selected point on the tie bar to raise its temperature to that approaching melting point and applying tension to the tie bar to part it. As shown, the apparatus comprises a shielded vessel 1 having a tube 3 suspended from a platform 2 the fuel element string 14 being lowered into the tube by a grab (not shown) through a pipe 4 closed by a valve 5. The string 14 is supported by a sleeve 13 movable along the tube 3 by a chain elevator 21. A tie bar puller 6 has a passage 7 leading to a magazine 8 for containing parted lengths of the bar. The bar is longer than the combined length of the fuel elements and is retained at the top end by a shield plug 16; hence, by adjusting the tube 3 a length of the bar may be exposed either at the lower end (as shown) adjacent the retaining nut 22 or at the top end adjacent the lower surface of the spiral neutron shield portion 17 of the plug 16. A heating source, e.g. a water-cooled induction coil (Fig. 2, not shown) is placed around the exposed length of the bar to heat it in the region 1000-1200 C., the puller 6 then being operated to part the bar. The first parting is made at the top end to separate the bar from the plug 16, the second and subsequent partings being made at the lower end, the bar being progressively pulled down through the string by the puller 6. The parted bar lengths in the magazine 8 are sent to a disposal void through a pipe 11.
GB25387/67A 1967-06-01 1967-06-01 Dismantling Fuel Element Strings for Nuclear Reactors Expired GB1176565A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB25387/67A GB1176565A (en) 1967-06-01 1967-06-01 Dismantling Fuel Element Strings for Nuclear Reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB25387/67A GB1176565A (en) 1967-06-01 1967-06-01 Dismantling Fuel Element Strings for Nuclear Reactors

Publications (1)

Publication Number Publication Date
GB1176565A true GB1176565A (en) 1970-01-07

Family

ID=10226852

Family Applications (1)

Application Number Title Priority Date Filing Date
GB25387/67A Expired GB1176565A (en) 1967-06-01 1967-06-01 Dismantling Fuel Element Strings for Nuclear Reactors

Country Status (1)

Country Link
GB (1) GB1176565A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2710181A1 (en) * 1993-09-13 1995-03-24 Cogema Method and device for induction cutting of elements of a nuclear installation.

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2710181A1 (en) * 1993-09-13 1995-03-24 Cogema Method and device for induction cutting of elements of a nuclear installation.

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