GB833647A - Improvements in or relating to nuclear reactors - Google Patents

Improvements in or relating to nuclear reactors

Info

Publication number
GB833647A
GB833647A GB10595/56A GB1059556A GB833647A GB 833647 A GB833647 A GB 833647A GB 10595/56 A GB10595/56 A GB 10595/56A GB 1059556 A GB1059556 A GB 1059556A GB 833647 A GB833647 A GB 833647A
Authority
GB
United Kingdom
Prior art keywords
core
graphite
pressure vessel
elements
reflector blocks
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
GB10595/56A
Inventor
Peter Fortescue
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
Priority to BE556417D priority Critical patent/BE556417A/xx
Application filed by UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to GB10595/56A priority patent/GB833647A/en
Priority to AU26775/57A priority patent/AU222480B1/en
Priority to FR1174121D priority patent/FR1174121A/en
Publication of GB833647A publication Critical patent/GB833647A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • 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
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/041—Means for removal of gases from fuel elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Particle Accelerators (AREA)
  • Carbon And Carbon Compounds (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

833,647. Nuclear reactors. UNITED KINGDOM ATOMIC ENERGY AUTHORITY April 2, 1957 [April 6, 1956], No. 10595/56. Class 39(4). In a gas cooled nuclear reactor, having very high heat release rates at high temperature, the core fuel elements and the reflector blocks are urged together by the cooling gas pressure and are mounted on pivots, at their lower ends, to allow for distortion and growth. The elements are arranged vertically in a central core surrounded by a ring of graphite reflector blocks containing vertical control rods movable in tubes, an outer ring of graphite reflector blocks, a steel cylindrical pressure vessel, a thermal shield comprising a hollow-walled, steel structure the voids in which contain water, and a concrete biological shield. Three separate gas cooling systems are provided, a vertical current of helium through the core, an air flow through the thermal shield, and a gas flow through the central rod tubes. In addition the interior of each core element is vented to a manifold outside the pressure vessel. Charging and discharging are effected through a vertical neck in the pressure vessel above the core. The neck is closed by a rotatable plug through which the elements are engaged by an arm carrying a grapple. Each core fuel element, Fig. 6, consists of an outer graphite tube 50 and a loose fitting inner graphite rod 60 having a helical groove 61. A helical strip 62 of fissile material, diluted with fertile material, is contained in 61, and a spacer 63 at each end of the element constitutes a neutron reflecting member. The graphite of the core may be in the proportion 3000 to 8000 parts by weight to one of the fissile material. The fissile and fertile materials are carburized after wrapping round the plug.
GB10595/56A 1956-04-06 1956-04-06 Improvements in or relating to nuclear reactors Expired GB833647A (en)

Priority Applications (4)

Application Number Priority Date Filing Date Title
BE556417D BE556417A (en) 1956-04-06
GB10595/56A GB833647A (en) 1956-04-06 1956-04-06 Improvements in or relating to nuclear reactors
AU26775/57A AU222480B1 (en) 1956-04-06 1957-04-04 Improvements in or relating to nuclear reactors
FR1174121D FR1174121A (en) 1956-04-06 1957-04-04 Nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB10595/56A GB833647A (en) 1956-04-06 1956-04-06 Improvements in or relating to nuclear reactors

Publications (1)

Publication Number Publication Date
GB833647A true GB833647A (en) 1960-04-27

Family

ID=9970732

Family Applications (1)

Application Number Title Priority Date Filing Date
GB10595/56A Expired GB833647A (en) 1956-04-06 1956-04-06 Improvements in or relating to nuclear reactors

Country Status (4)

Country Link
AU (1) AU222480B1 (en)
BE (1) BE556417A (en)
FR (1) FR1174121A (en)
GB (1) GB833647A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1187332B (en) * 1960-09-16 1965-02-18 Interatom Fuel element for nuclear reactors
DE1233505B (en) * 1961-03-09 1967-02-02 Anglo Belge Vulcain Sa Soc Reactor core component
DE1295717B (en) * 1962-09-15 1969-05-22 Kernforschung Gmbh Ges Fuer Nuclear reactor fuel assembly made from nuclear fuel rods that are long in relation to their diameter and nuclear reactor fuel assembly made from these fuel assemblies

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3124514A (en) * 1964-03-10 koutz etal
FR1234258A (en) * 1959-05-13 1960-10-17 Fuel rod with internal channels for nuclear reactor
DE1220943B (en) * 1959-06-16 1966-07-14 Atomic Energy Authority Uk Support for the core arrangement of an atomic nuclear reactor
US3146173A (en) * 1960-03-07 1964-08-25 Fortescue Peter Fuel element
US3100187A (en) * 1961-05-03 1963-08-06 Arthur P Fraas Reflector for neutronic reactors
BE633135A (en) * 1962-06-04
SE324019B (en) * 1968-12-02 1970-05-19 Asea Ab

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1187332B (en) * 1960-09-16 1965-02-18 Interatom Fuel element for nuclear reactors
DE1233505B (en) * 1961-03-09 1967-02-02 Anglo Belge Vulcain Sa Soc Reactor core component
DE1295717B (en) * 1962-09-15 1969-05-22 Kernforschung Gmbh Ges Fuer Nuclear reactor fuel assembly made from nuclear fuel rods that are long in relation to their diameter and nuclear reactor fuel assembly made from these fuel assemblies

Also Published As

Publication number Publication date
BE556417A (en)
FR1174121A (en) 1959-03-06
AU222480B1 (en) 1957-10-10

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