GB1217141A - Nuclear reactors - Google Patents

Nuclear reactors

Info

Publication number
GB1217141A
GB1217141A GB5908/67A GB590867A GB1217141A GB 1217141 A GB1217141 A GB 1217141A GB 5908/67 A GB5908/67 A GB 5908/67A GB 590867 A GB590867 A GB 590867A GB 1217141 A GB1217141 A GB 1217141A
Authority
GB
United Kingdom
Prior art keywords
fuel
core
vessel
assembly
stringers
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
GB5908/67A
Inventor
Robert James Perrett
James Milne Mackinnon
James Malcolm Parker
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.)
English Electric Co Ltd
Original Assignee
English Electric Co 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 English Electric Co Ltd filed Critical English Electric Co Ltd
Priority to GB5908/67A priority Critical patent/GB1217141A/en
Priority to BE710142D priority patent/BE710142A/xx
Publication of GB1217141A publication Critical patent/GB1217141A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C5/00Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02Details
    • G21C5/08Means for preventing undesired asymmetric expansion of the complete structure ; Stretching devices, pins
    • 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

1,217,141. Moderator structures. ENGLISH ELECTRIC CO. Ltd. 5 Feb., 1968 [7 Feb., 1967], No. 5908/67. Heading G6C. In a nuclear reactor concrete pressure vessel, the graphite moderator block assembly is arranged in columns, has a side restraining structure surrounding the assembly and is located within the vessel by keys engaging the vessel side walls. Distortion of the pressure vessel is accompanied by a corresponding distortion of the assembly upper region, by reason of the keys, so that alignment between the standpipes and the core fuel tubes is maintained. Twisting movement of the vessel is transmitted to the core through the keys and the side restraining structure. The core is carried upon a perforated plate which is supported upon the pressure vessel floor by pillars which rock about their lower ends to permit plate radial expansion. Coolant gas is pumped through the core base upwards through the fuel stringers. Gas also passes round the moderator assembly and enters it through the upper surface before passing downwards in the interstitial spaces between the columns. A further flow occurs downwardly in the annular spaces between the fuel stringers and the fuel channel walls. The flow in the core interstitial spaces enters the fuel stringers at the lower ends. Each fuel channel contains a debris collector.
GB5908/67A 1967-02-07 1967-02-07 Nuclear reactors Expired GB1217141A (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
GB5908/67A GB1217141A (en) 1967-02-07 1967-02-07 Nuclear reactors
BE710142D BE710142A (en) 1967-02-07 1968-01-31

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB5908/67A GB1217141A (en) 1967-02-07 1967-02-07 Nuclear reactors

Publications (1)

Publication Number Publication Date
GB1217141A true GB1217141A (en) 1970-12-31

Family

ID=9804886

Family Applications (1)

Application Number Title Priority Date Filing Date
GB5908/67A Expired GB1217141A (en) 1967-02-07 1967-02-07 Nuclear reactors

Country Status (2)

Country Link
BE (1) BE710142A (en)
GB (1) GB1217141A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2462000A1 (en) * 1979-07-23 1981-02-06 Hochtemperatur Reaktorbau Gmbh CARRIER BASE FORMED OF A LARGE NUMBER OF GRAPHITE BLOCKS FOR THE HEART OF A NUCLEAR REACTOR WITH SPHERICAL FUEL ELEMENTS
US4290852A (en) * 1978-04-21 1981-09-22 Hochtemperatur-Reaktorbau Gmbh Roof reflector for a gas-cooled pebble-bed reactor and process for the disassembly of the roof reflector
US5588031A (en) * 1994-10-27 1996-12-24 Westinghouse Electric Corporation Apparatus for reinforcing a reactor vessel core shroud

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114446497B (en) * 2022-02-17 2024-04-19 中国核动力研究设计院 Ultra-high flux reactor core based on square fuel assembly

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4290852A (en) * 1978-04-21 1981-09-22 Hochtemperatur-Reaktorbau Gmbh Roof reflector for a gas-cooled pebble-bed reactor and process for the disassembly of the roof reflector
FR2462000A1 (en) * 1979-07-23 1981-02-06 Hochtemperatur Reaktorbau Gmbh CARRIER BASE FORMED OF A LARGE NUMBER OF GRAPHITE BLOCKS FOR THE HEART OF A NUCLEAR REACTOR WITH SPHERICAL FUEL ELEMENTS
US5588031A (en) * 1994-10-27 1996-12-24 Westinghouse Electric Corporation Apparatus for reinforcing a reactor vessel core shroud

Also Published As

Publication number Publication date
BE710142A (en) 1968-05-30

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