GB1528012A - Nuclear reactor refuelling system - Google Patents

Nuclear reactor refuelling system

Info

Publication number
GB1528012A
GB1528012A GB28532/75A GB2853275A GB1528012A GB 1528012 A GB1528012 A GB 1528012A GB 28532/75 A GB28532/75 A GB 28532/75A GB 2853275 A GB2853275 A GB 2853275A GB 1528012 A GB1528012 A GB 1528012A
Authority
GB
United Kingdom
Prior art keywords
bucket
rails
pair
duct
ramp means
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
GB28532/75A
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 GB28532/75A priority Critical patent/GB1528012A/en
Publication of GB1528012A publication Critical patent/GB1528012A/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
    • G21C19/32Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage place; Apparatus for handling radioactive objects or materials within a storage place or removing them therefrom
    • 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)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

1528012 Fuelling reactors UNITED KING- DOM ATOMIC ENERGY AUTHORITY 7 June 1976 [7 July 1975] 28532/75 Heading G6C A handling system for fuel element assemblies of a liquid metal cooled nuclear reactor comprises a transfer bucket and ramp means for guiding the bucket for lifting or lowering in a direction inclined to the vertical, a branch of the ramp means causing a change of attitude of the bucket between parallelism with the ramp means and a vertical attitude. As shown, the ramp means comprises two pairs of inclined parallel rails 10, 11 (only one rail of each pair being shown), the inner pair 11 having a branch in the lower end region which is inclined at a steeper angle than the parent rails, and the transfer bucket 2 has two longitudinally spaced pairs of trunnions 6, 7 of which the upper pair 6 are in engagement with the outer rails 10 whilst the lower pair 7 project less than the upper pair 6 so that they are capable of engaging only the inner rails 11. At the exchange position 1, a fuel element assembly can be manipulated by a charge/discharge machine (not shown) into and out of the transfer bucket 2 within a pool 4 of molten sodium, the upper end of which bucket 2 abuts a pad 8 on the vertical surface 3 of the reactor core vessel whilst its tapering lower end 5 fits within a socket 9. The interior of the socket 9 tapers in complementary manner to the lower end 5 of the bucket 2 and provides an opening 13 at its upper end which is wider than the bucket 2. The socket 9 is mounted on a shock absorber 12, which absorbs energy should a fuel element assembly be inadvertently dropped into the bucket 2, or should the bucket 2 be released inadvertently to run out of control down the rails 10, 11. The bucket 2 may be drawn along the rails 10, 11 by a chain drive (not shown) extending parallel with the rails 10, 11 and attached to the trunnions 6. Although not shown in the drawing, the upper region of a duct 14 housing the rails 10, 11 is surrounded by an annular coaxial duct whereby argon cooling gas can be passed through the inner duct 14 in heat exchange with the bucket 2 and returned through the outer duct to gas circulating means situated outside the reactor vault.
GB28532/75A 1976-06-07 1976-06-07 Nuclear reactor refuelling system Expired GB1528012A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB28532/75A GB1528012A (en) 1976-06-07 1976-06-07 Nuclear reactor refuelling system

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB28532/75A GB1528012A (en) 1976-06-07 1976-06-07 Nuclear reactor refuelling system

Publications (1)

Publication Number Publication Date
GB1528012A true GB1528012A (en) 1978-10-11

Family

ID=10277129

Family Applications (1)

Application Number Title Priority Date Filing Date
GB28532/75A Expired GB1528012A (en) 1976-06-07 1976-06-07 Nuclear reactor refuelling system

Country Status (1)

Country Link
GB (1) GB1528012A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2147137A (en) * 1983-09-23 1985-05-01 Westinghouse Electric Corp Fuel transfer system upender using translation drive
FR2993091A1 (en) * 2012-07-05 2014-01-10 Commissariat Energie Atomique Installation unit for handling worn out fuel assemblies of sodium-cooled nuclear reactor vessel of nuclear power plant, has transfer unit transferring container to truck in transfer position when another truck is in extraction position
CN106504806A (en) * 2016-12-29 2017-03-15 中广核研究院有限公司 A kind of soft drive and emergency trip device

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2147137A (en) * 1983-09-23 1985-05-01 Westinghouse Electric Corp Fuel transfer system upender using translation drive
US4717531A (en) * 1983-09-23 1988-01-05 Westinghouse Electric Corp. Fuel transfer system upender using translation drive
FR2993091A1 (en) * 2012-07-05 2014-01-10 Commissariat Energie Atomique Installation unit for handling worn out fuel assemblies of sodium-cooled nuclear reactor vessel of nuclear power plant, has transfer unit transferring container to truck in transfer position when another truck is in extraction position
CN106504806A (en) * 2016-12-29 2017-03-15 中广核研究院有限公司 A kind of soft drive and emergency trip device

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Legal Events

Date Code Title Description
PS Patent sealed
PCNP Patent ceased through non-payment of renewal fee