GB1264473A - - Google Patents

Info

Publication number
GB1264473A
GB1264473A GB868868A GB1264473DA GB1264473A GB 1264473 A GB1264473 A GB 1264473A GB 868868 A GB868868 A GB 868868A GB 1264473D A GB1264473D A GB 1264473DA GB 1264473 A GB1264473 A GB 1264473A
Authority
GB
United Kingdom
Prior art keywords
guide tube
tube
standpipe
membrane
fuel
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
GB868868A
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 filed Critical
Publication of GB1264473A publication Critical patent/GB1264473A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C13/00Pressure vessels; Containment vessels; Containment in general
    • G21C13/02Details
    • G21C13/04Arrangements for expansion and contraction
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C13/00Pressure vessels; Containment vessels; Containment in general
    • G21C13/02Details
    • 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

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Separation Using Semi-Permeable Membranes (AREA)

Abstract

1,264,473. Reactors. BRITISH NUCLEAR DESIGN & CONSTRUCTION Ltd. 21 Feb., 1969 [22 Feb., 1968], No. 8688/68. Heading G6C. In a guide tube arrangement for a re-entrant type gas-cooled nuclear reactor, the guide tube 4 extends between a pressure vessel standpipe 1 and a corresponding fuel or control rod channel 6, and passes through an aperture 11 in a pressure membrane 8 and through a tube 13 which is shorter than the guide tube 4, one end of the tube 13 being attached and sealed to the membrane 8 and the other end being attached and sealed to the guide tube 4 at a point intermediate along its length. Relative movement between the membrane 8 and the standpipe 1 is accommodated in the plane of the membrane 8 by the flexibility of the guide tube 4 and the tube 13, and in a perpendicular direction by relative axial movement permitted the ends of the guide tube 4. The guide tube 4 is in two parts 4A, 4B, the upper part 4A being provided with an enlarged head portion 16 which is a sliding fit within an enlarged bore portion 3 of the standpipe 1, and with a flange 17 at its lower end, while the lower part 4B is provided with a flange 18 at its upper end and with circumferentially spaced ribs 19 at its lower end which are a sliding fit in an enlarged bore portion 5 of the channel 6. The end wall 14 of the tube 13 and the flanges 17, 18 of the guide tube parts 4A, 4B are rigidly connected and sealed together. The diameters of the channel 6, the guide tube 4 and the smaller diameter portion of the standpipe 1 are substantially the same and are just sufficient to accommodate fuel element strings (not shown), so as to reduce the possibility of the strings rattling whilst being transferred from a suitable charge/servicing machine into the reactor core 7. During operation of the reactor, cool gas flows down through the annular passage defined between the fuel channel 6 and the fuel sleeve assembly 20 and is joined at the bottom of the reactor core 7 by further coolant fed to below the core. The coolant is returned through the fuel sleeve bore 21, and thence to the hot-box 9 by way of the guide tube 4 and ports 4C.
GB868868A 1968-02-22 1968-02-22 Expired GB1264473A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB868868 1968-02-22

Publications (1)

Publication Number Publication Date
GB1264473A true GB1264473A (en) 1972-02-23

Family

ID=9857328

Family Applications (1)

Application Number Title Priority Date Filing Date
GB868868A Expired GB1264473A (en) 1968-02-22 1968-02-22

Country Status (1)

Country Link
GB (1) GB1264473A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111194470A (en) * 2017-06-23 2020-05-22 坎杜能源公司 System and method for arranging nuclear reactor tubes and end fittings using tube rotation

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111194470A (en) * 2017-06-23 2020-05-22 坎杜能源公司 System and method for arranging nuclear reactor tubes and end fittings using tube rotation
CN111194470B (en) * 2017-06-23 2023-09-22 坎杜能源公司 System and method for arranging nuclear reactor tubes and end fittings using tube rotation

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Legal Events

Date Code Title Description
PS Patent sealed
PLNP Patent lapsed through nonpayment of renewal fees