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GB1129363A - Nuclear reactors - Google Patents

Nuclear reactors

Info

Publication number
GB1129363A
GB1129363A GB29057/65A GB2905765A GB1129363A GB 1129363 A GB1129363 A GB 1129363A GB 29057/65 A GB29057/65 A GB 29057/65A GB 2905765 A GB2905765 A GB 2905765A GB 1129363 A GB1129363 A GB 1129363A
Authority
GB
United Kingdom
Prior art keywords
graphite
neutron shield
plenum
fuel channels
moderator
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
GB29057/65A
Inventor
Leonard Edward Wallhead
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 GB29057/65A priority Critical patent/GB1129363A/en
Priority to FR65566A priority patent/FR1483407A/en
Priority to DE19661539917 priority patent/DE1539917B/de
Publication of GB1129363A publication Critical patent/GB1129363A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
    • G21C1/326—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core wherein the heat exchanger is disposed next to or beside the core
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • G21C1/022—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders characterised by the design or properties of the core
    • G21C1/024—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders characterised by the design or properties of the core where the core is divided in zones with fuel and zones with breeding material
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • G21C1/10—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated
    • G21C1/12—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor or gas-graphite reactor
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C11/00—Shielding structurally associated with the reactor
    • G21C11/02—Biological shielding ; Neutron or gamma shielding
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C11/00—Shielding structurally associated with the reactor
    • G21C11/02—Biological shielding ; Neutron or gamma shielding
    • G21C11/022—Biological shielding ; Neutron or gamma shielding inside the reactor vessel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C11/00—Shielding structurally associated with the reactor
    • G21C11/02—Biological shielding ; Neutron or gamma shielding
    • G21C11/028—Biological shielding ; Neutron or gamma shielding characterised by the form or by the material
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C11/00—Shielding structurally associated with the reactor
    • G21C11/08—Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield ; Thermal insulation
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/08—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from moderating material
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/10—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from reflector or thermal shield
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/22—Structural association of coolant tubes with headers
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02—Details
    • G21C5/08—Means for preventing undesired asymmetric expansion of the complete structure ; Stretching devices, pins
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02—Details
    • G21C5/10—Means for supporting the complete structure
    • Y—GENERAL 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • Biomedical Technology (AREA)
  • General Health & Medical Sciences (AREA)
  • Molecular Biology (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Health & Medical Sciences (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Particle Accelerators (AREA)

Abstract

1,129,363. Reactors. ENGLISH ELECTRIC CO. Ltd. 6 July, 1966 [8 July, 1965], No. 29057/65. Heading G6C. A gas-cooled nuclear reactor comprises a pressure vessel within which is supported a graphite structure including a graphite moderator having longitudinally-extending fuel channels, the exit ends of which communicate with a transverse coolant gas outlet plenum disposed intermediately between the ends of the graphite structure, means being provided for removing coolant gas from the outlet plenum in a direction transverse with respect to the fuel channels. The graphite structure is supported on a floor of the pressure vessel by support means, the fuel channels being arranged vertically for downward flow of the coolant gas, e.g. helium, and the outlet plenum is separated from the support means by a part of the graphite structure. The graphite structure preferably includes a transverse graphite neutron shield disposed below the moderator, at least part of the neutron shield being below the plenum. The neutron shield may comprise at least one layer of solid graphite bricks, the moderator consisting of a plurality of moderator columns, at least some of which have fuel channels formed therein, supported on the neutron shield through a plurality of pillars, preferably of graphite, passing through the plenum. The pillars are hollow and provided with ports for bringing the corresponding fuel channels into communication with the plenum. The pressure vessel is preferably of concrete. The support means may comprise a plurality of support columns extending above the floor and supporting the neutron shield, e.g. through thermal insulating plate means. Preferably, cooling means are provided for circulation of a cooling fluid around the support means and through the neutron shield.
GB29057/65A 1965-07-08 1965-07-08 Nuclear reactors Expired GB1129363A (en)

Priority Applications (3)

Application Number Priority Date Filing Date Title
GB29057/65A GB1129363A (en) 1965-07-08 1965-07-08 Nuclear reactors
FR65566A FR1483407A (en) 1965-07-08 1966-06-15 Nuclear reactor
DE19661539917 DE1539917B (en) 1965-07-08 1966-07-08

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB29057/65A GB1129363A (en) 1965-07-08 1965-07-08 Nuclear reactors

Publications (1)

Publication Number Publication Date
GB1129363A true GB1129363A (en) 1968-10-02

Family

ID=10285513

Family Applications (1)

Application Number Title Priority Date Filing Date
GB29057/65A Expired GB1129363A (en) 1965-07-08 1965-07-08 Nuclear reactors

Country Status (2)

Country Link
DE (1) DE1539917B (en)
GB (1) GB1129363A (en)

Cited By (2)

* 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
US4849157A (en) * 1983-12-15 1989-07-18 Interatom Gmbh Core barrel for a high-temperature nuclear reactor

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2411039C2 (en) * 1974-03-08 1983-01-05 Hochtemperatur-Reaktorbau GmbH, 5000 Köln Nuclear power plant with closed gas cooling circuit for generating process heat
DE2414757C2 (en) * 1974-03-27 1984-06-14 Interatom Internationale Atomreaktorbau Gmbh, 5060 Bergisch Gladbach Reflector cooling for pebble bed reactors

Cited By (2)

* 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
US4849157A (en) * 1983-12-15 1989-07-18 Interatom Gmbh Core barrel for a high-temperature nuclear reactor

Also Published As

Publication number Publication date
DE1539917B (en) 1971-01-14

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