GB908456A - Improvements in or relating to nuclear reactor control elements - Google Patents

Improvements in or relating to nuclear reactor control elements

Info

Publication number
GB908456A
GB908456A GB16445/60A GB1644560A GB908456A GB 908456 A GB908456 A GB 908456A GB 16445/60 A GB16445/60 A GB 16445/60A GB 1644560 A GB1644560 A GB 1644560A GB 908456 A GB908456 A GB 908456A
Authority
GB
United Kingdom
Prior art keywords
nuclear reactor
neutron absorbing
boron steel
neutron
relating
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
GB16445/60A
Inventor
Frank Marsden Leslie
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 GB16445/60A priority Critical patent/GB908456A/en
Priority to DEU8006A priority patent/DE1208424B/en
Priority to FR861314A priority patent/FR1289107A/en
Publication of GB908456A publication Critical patent/GB908456A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C9/00Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/02Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
    • G21C9/027Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency by fast movement of a solid, e.g. pebbles
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C9/00Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/02Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C9/00Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/02Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
    • G21C9/022Reactor fuses
    • 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)
  • Particle Accelerators (AREA)

Abstract

908,456. Nuclear reactor control rods. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. May 5, 1961 [May 10, 1960], No. 16445/60. Class 39 (4). A control device for a pressurized gas-cooled nuclear reactor comprises a neutron absorbing body 5 housed within a neutron absorbing body 4 in a container 3 in a vertical channel in the reactor core, and means for releasing the body 5 so that it falls under gravity, thus increasing the neutron absorption capacity of the device. In the device shown, on a sudden reduction of coolant gas pressure, gas escapes more quickly through holes 22, 23 than through hole 21, thus creating a pressure difference across diaphragm 11 which moves and lowers plug 13, allowing boron steel shot 5 to fall out of boron steel tube 4 into tube 18. Other neutron absorbing elements referred to are cadmium, mercury and rare earths.
GB16445/60A 1960-05-10 1960-05-10 Improvements in or relating to nuclear reactor control elements Expired GB908456A (en)

Priority Applications (3)

Application Number Priority Date Filing Date Title
GB16445/60A GB908456A (en) 1960-05-10 1960-05-10 Improvements in or relating to nuclear reactor control elements
DEU8006A DE1208424B (en) 1960-05-10 1961-05-09 Shutdown device for gas-cooled nuclear reactors
FR861314A FR1289107A (en) 1960-05-10 1961-05-09 Regulating device for nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB16445/60A GB908456A (en) 1960-05-10 1960-05-10 Improvements in or relating to nuclear reactor control elements

Publications (1)

Publication Number Publication Date
GB908456A true GB908456A (en) 1962-10-17

Family

ID=10077449

Family Applications (1)

Application Number Title Priority Date Filing Date
GB16445/60A Expired GB908456A (en) 1960-05-10 1960-05-10 Improvements in or relating to nuclear reactor control elements

Country Status (2)

Country Link
DE (1) DE1208424B (en)
GB (1) GB908456A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4104121A (en) * 1972-06-02 1978-08-01 Groupement Atomique Alsacienne Atlantique Solid absorbent safety device for a nuclear reactor
FR2394147A1 (en) * 1977-06-10 1979-01-05 Combustion Eng DEVICE FOR RETAINING, RELEASING AND REPLACING NEUTRON ABSORPTION MASSES
US4407774A (en) * 1976-07-23 1983-10-04 Kernforschungszentrum Karlsruhe G.M.B.H. Method for preventing dangerous hydrogen accumulation in nuclear reactor containments

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1052000B (en) * 1957-12-13 1959-03-05 Siemens Ag Shutdown device for liquid-cooled nuclear reactors

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4104121A (en) * 1972-06-02 1978-08-01 Groupement Atomique Alsacienne Atlantique Solid absorbent safety device for a nuclear reactor
US4407774A (en) * 1976-07-23 1983-10-04 Kernforschungszentrum Karlsruhe G.M.B.H. Method for preventing dangerous hydrogen accumulation in nuclear reactor containments
FR2394147A1 (en) * 1977-06-10 1979-01-05 Combustion Eng DEVICE FOR RETAINING, RELEASING AND REPLACING NEUTRON ABSORPTION MASSES

Also Published As

Publication number Publication date
DE1208424B (en) 1966-01-05

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