GB1184188A - Improvements in or relating to Nuclear Reactors - Google Patents

Improvements in or relating to Nuclear Reactors

Info

Publication number
GB1184188A
GB1184188A GB47423/66A GB4742366A GB1184188A GB 1184188 A GB1184188 A GB 1184188A GB 47423/66 A GB47423/66 A GB 47423/66A GB 4742366 A GB4742366 A GB 4742366A GB 1184188 A GB1184188 A GB 1184188A
Authority
GB
United Kingdom
Prior art keywords
component
fuel
stringer
channel
fuel elements
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
GB47423/66A
Inventor
Gordon Packman
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 GB47423/66A priority Critical patent/GB1184188A/en
Priority to DE19671614941 priority patent/DE1614941A1/en
Priority to FR1557704D priority patent/FR1557704A/fr
Priority to BE705451D priority patent/BE705451A/xx
Publication of GB1184188A publication Critical patent/GB1184188A/en
Expired 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
    • G21C19/02Details of handling arrangements
    • G21C19/04Means for controlling flow of coolant over objects being handled; Means for controlling flow of coolant through channel being serviced, e.g. for preventing "blow-out"
    • 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)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

1,184,188. Fuel elements. UNITED KING- DOM ATOMIC ENERGY AUTHORITY. 10 Oct., 1967 [21 Oct., 1966], No. 47423/66. Heading G6C. The levitation of a fuel stringer within a fuel channel of a nuclear reactor is resisted by the use of a coolant pressure difference. In the embodiment illustrated, a component 1 of a fuel stringer, e.g. a neutron scattering plug, has an extension 3 of reduced external size, a further component 4 sealing between the extension 3 and the wall 2 of the fuel channel. The component 4 has a pair of sliding seals 5 contacting the wall 2 and a pair of sliding seals 6 contacting the extension 3, and is held stationary with respect to the channel. As described in Specification 882,714, part of the fuel coolant flow, i.e. pressurized gas, is introduced at a pressure in excess of that prevailing elsewhere in the channel by means of passages 7 into the annulus between the component 1 and the channel wall 2 and flows downwards through the core at the bottom of which it joins other coolant flow and passes up through the interiors of the fuel elements of the stringer and the component 1. The pressurized gas from the passages 7 enters the space between the components 1 and 4, the component 1 acting as a plunger exerting a downward pressure on the sleeves of the fuel elements on which it rests. Levitation of the fuel elements is thus resisted. The component 4 carries a spider 8 through which extends a tie-rod 9 having an upper termination 10 which, after the spider is raised a short distance, abuts on the spider and lifts the tie-rod 9, this in turn raising the fuel elements. A connection 12 releasably connects a component 11 to the component 4. The component 11 is normally a spacing piece connecting the fuel and neutron plug parts of the stringer with parts having a gag valve and a shield and seal plug serving to close the respective refuelling access aperture in the reactor pressure vessel. The component 4 has a lost motion interconnection 18 with the component 1 consisting of abutments 19 and 20 adapted to cooperate after a certain degree of raising of component 4 relative to component 1 in excess of the abovementioned short distance. On raising the stringer, an upward pull on component 11 is transmitted to component 4 which when raised beyond the short distance lifts the fuel elements. The pressure resisting levitation continues to hold down component 1 until the seals 5 are clear of the channel. The abutments 19 and 20 are not brought into contact until after removal of the stringer from the reactor when they support the component 1 after the tie-rod 9 has been severed. The force resisting levitation may, if desired, be utilized only during refuelling by arranging components 1 and 4 so that they completely close together when the stringer is fully inserted with the weight of component 4 holding down component 1.
GB47423/66A 1966-10-21 1966-10-21 Improvements in or relating to Nuclear Reactors Expired GB1184188A (en)

Priority Applications (4)

Application Number Priority Date Filing Date Title
GB47423/66A GB1184188A (en) 1966-10-21 1966-10-21 Improvements in or relating to Nuclear Reactors
DE19671614941 DE1614941A1 (en) 1966-10-21 1967-10-20 Nuclear reactor
FR1557704D FR1557704A (en) 1966-10-21 1967-10-20
BE705451D BE705451A (en) 1966-10-21 1967-10-20

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB47423/66A GB1184188A (en) 1966-10-21 1966-10-21 Improvements in or relating to Nuclear Reactors

Publications (1)

Publication Number Publication Date
GB1184188A true GB1184188A (en) 1970-03-11

Family

ID=10444914

Family Applications (1)

Application Number Title Priority Date Filing Date
GB47423/66A Expired GB1184188A (en) 1966-10-21 1966-10-21 Improvements in or relating to Nuclear Reactors

Country Status (4)

Country Link
BE (1) BE705451A (en)
DE (1) DE1614941A1 (en)
FR (1) FR1557704A (en)
GB (1) GB1184188A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4875661A (en) * 1984-09-07 1989-10-24 Langston Ralph C Method for pulling multiple runs of fiber optic cable

Also Published As

Publication number Publication date
FR1557704A (en) 1969-02-21
DE1614941A1 (en) 1970-05-27
BE705451A (en) 1968-03-01

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Legal Events

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