GB1086054A - Improvements relating to supporting platforms for nuclear reactors - Google Patents

Improvements relating to supporting platforms for nuclear reactors

Info

Publication number
GB1086054A
GB1086054A GB18929/63A GB1892963A GB1086054A GB 1086054 A GB1086054 A GB 1086054A GB 18929/63 A GB18929/63 A GB 18929/63A GB 1892963 A GB1892963 A GB 1892963A GB 1086054 A GB1086054 A GB 1086054A
Authority
GB
United Kingdom
Prior art keywords
sectors
platform
improvements relating
nuclear reactors
supporting platforms
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
GB18929/63A
Inventor
Leonard Maxwell Hoskins
Edward Carlos Derbyshire
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.)
WFEL Ltd
Original Assignee
Fairey Engineering Ltd
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 Fairey Engineering Ltd filed Critical Fairey Engineering Ltd
Priority to GB18929/63A priority Critical patent/GB1086054A/en
Publication of GB1086054A publication Critical patent/GB1086054A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/30Subcritical reactors ; Experimental reactors other than swimming-pool reactors or zero-energy reactors
    • G21C1/303Experimental or irradiation arrangements inside the reactor
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C13/00Pressure vessels; Containment vessels; Containment in general
    • G21C13/02Details
    • G21C13/024Supporting constructions for pressure vessels or containment vessels
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C5/00Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02Details
    • G21C5/10Means for supporting the complete structure
    • 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)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

1,086,054. Reactors. FAIREY ENGINEERING Ltd. Aug. 12, 1964 [May 13, 1963], No. 18929/63. Heading G6C. In a zero-energy, experimental, gas-cooled, reactor the circumferential portion of the graphite moderator is supported on an accurately levelled annular platform. The reactor control test region is supported separately and is screened from the circumferential part by a thermal barrier. The annular platform is formed of interlocking steel sectors each of which rests on three vertically-adjustable supporting screws. Each sector has stabilizing screws to prevent tilting and locating pins are provided to maintain the platform in position on a base. The radial edges of the sectors are pinned together to form seals.
GB18929/63A 1963-05-13 1963-05-13 Improvements relating to supporting platforms for nuclear reactors Expired GB1086054A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB18929/63A GB1086054A (en) 1963-05-13 1963-05-13 Improvements relating to supporting platforms for nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB18929/63A GB1086054A (en) 1963-05-13 1963-05-13 Improvements relating to supporting platforms for nuclear reactors

Publications (1)

Publication Number Publication Date
GB1086054A true GB1086054A (en) 1967-10-04

Family

ID=10120889

Family Applications (1)

Application Number Title Priority Date Filing Date
GB18929/63A Expired GB1086054A (en) 1963-05-13 1963-05-13 Improvements relating to supporting platforms for nuclear reactors

Country Status (1)

Country Link
GB (1) GB1086054A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0053553A1 (en) * 1980-11-28 1982-06-09 Framatome Reactor building having its internal structures independent of the foundation raft, and method of building these structures
EP0222581A2 (en) * 1985-11-06 1987-05-20 Westinghouse Electric Corporation Method of mounting a core barrel in a pressure vessel of a nuclear reactor
CN114049974A (en) * 2021-10-29 2022-02-15 上海市安装工程集团有限公司 Nuclear energy experiment stack assembly adjusting rack and using method thereof

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0053553A1 (en) * 1980-11-28 1982-06-09 Framatome Reactor building having its internal structures independent of the foundation raft, and method of building these structures
US4476087A (en) * 1980-11-28 1984-10-09 Framatome Reactor building
EP0222581A2 (en) * 1985-11-06 1987-05-20 Westinghouse Electric Corporation Method of mounting a core barrel in a pressure vessel of a nuclear reactor
EP0222581A3 (en) * 1985-11-06 1988-01-27 Westinghouse Electric Corporation Core barrel support system for nuclear reactors
US4756877A (en) * 1985-11-06 1988-07-12 Westinghouse Electric Corp. Core barrel support system for nuclear reactors
CN114049974A (en) * 2021-10-29 2022-02-15 上海市安装工程集团有限公司 Nuclear energy experiment stack assembly adjusting rack and using method thereof
CN114049974B (en) * 2021-10-29 2024-05-03 上海市安装工程集团有限公司 Nuclear energy experimental reactor assembly adjustment bench and use method thereof

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