GB1390907A - Controlling nuclear reactors - Google Patents

Controlling nuclear reactors

Info

Publication number
GB1390907A
GB1390907A GB6110670A GB6110670A GB1390907A GB 1390907 A GB1390907 A GB 1390907A GB 6110670 A GB6110670 A GB 6110670A GB 6110670 A GB6110670 A GB 6110670A GB 1390907 A GB1390907 A GB 1390907A
Authority
GB
United Kingdom
Prior art keywords
flow rate
main
core
reactor
boilers
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
GB6110670A
Inventor
Victor George Brian
Arthur Ward Deon
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.)
British Nuclear Design of Construction Ltd
Original Assignee
British Nuclear Design of Construction 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 British Nuclear Design of Construction Ltd filed Critical British Nuclear Design of Construction Ltd
Priority to GB6110670A priority Critical patent/GB1390907A/en
Publication of GB1390907A publication Critical patent/GB1390907A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/32Control of nuclear reaction by varying flow of coolant through the core by adjusting the coolant or moderator temperature
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/06Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/22Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of a fluid or fluent neutron-absorbing material, e.g. by adding neutron-absorbing material to the coolant
    • 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)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Polymerisation Methods In General (AREA)

Abstract

1390907 Controlling nuclear reactors BRITISH NUCLEAR DESIGN & CONSTRUCTION Ltd 23 March 1972 [23 Dec 1970] 61106/70 Heading G6C A fluid-cooled reactor (e.g. helium-cooled HRT). with a core negative temperature coefficient of reactivity is controlled, to produce a rapid reduction in core thermal output, by reducing the coolant mass flow rate whereby the temperature rises and reactivity falls. The flow rate reduction may be effected by shutting down main boilers and coolant circulators while leaving auxiliary boilers and circulators operative. Simultaneously with the flow rate reduction, some of a group of control rods are introduced into the core to reduce its thermal output by an amount less than would accord with the reduced flow rate. The temperature rise is thus such as not to initiate a full reactor shut-down by tripping energency shut-down systems. The procedure is invoked when a short-term fault in the main turbogenerator or grid results in a decrease in demand on the reactor. The arrangement of main and auxiliary boilers is as disclosed in Specification 1,368,954.
GB6110670A 1970-12-23 1970-12-23 Controlling nuclear reactors Expired GB1390907A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB6110670A GB1390907A (en) 1970-12-23 1970-12-23 Controlling nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB6110670A GB1390907A (en) 1970-12-23 1970-12-23 Controlling nuclear reactors

Publications (1)

Publication Number Publication Date
GB1390907A true GB1390907A (en) 1975-04-16

Family

ID=10486617

Family Applications (1)

Application Number Title Priority Date Filing Date
GB6110670A Expired GB1390907A (en) 1970-12-23 1970-12-23 Controlling nuclear reactors

Country Status (1)

Country Link
GB (1) GB1390907A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2008123832A1 (en) * 2007-04-10 2008-10-16 Westinghouse Electric Sweden Ab A method for operating a reactor of a nuclear plant

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2008123832A1 (en) * 2007-04-10 2008-10-16 Westinghouse Electric Sweden Ab A method for operating a reactor of a nuclear plant
US8477899B2 (en) 2007-04-10 2013-07-02 Westinghouse Electric Sweden Ab Method for operating a reactor of a nuclear plant

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Legal Events

Date Code Title Description
PS Patent sealed
PLNP Patent lapsed through nonpayment of renewal fees