GB887392A - Improvements in or relating to control apparatus for nuclear reactors - Google Patents

Improvements in or relating to control apparatus for nuclear reactors

Info

Publication number
GB887392A
GB887392A GB23106/59A GB2310659A GB887392A GB 887392 A GB887392 A GB 887392A GB 23106/59 A GB23106/59 A GB 23106/59A GB 2310659 A GB2310659 A GB 2310659A GB 887392 A GB887392 A GB 887392A
Authority
GB
United Kingdom
Prior art keywords
reactor
control term
temperature
output
term
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
GB23106/59A
Inventor
Ronald Hugh Campbell
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 GB23106/59A priority Critical patent/GB887392A/en
Priority claimed from FR831969A external-priority patent/FR1261673A/en
Publication of GB887392A publication Critical patent/GB887392A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/36Control circuits
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/10Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/112Measuring temperature
    • 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)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

887,392. Nuclear reactors. UNITED KING- DOM ATOMIC ENERGY AUTHORITY. June 17, 1960 [July 6, 1959], No. 23106/59. Class 39(4) A control apparatus for a nuclear reactor comprises means for deriving a primary control term from a temperature measurement taken at a point in the reactor core, means for deriving an additional control term as a function of reactor flux and coolant flow, and means for combining the two terms to provide a composite control term. In the Figure the reactor is provided with a plurality of thermocouples 18 (of which only one is shown) for measuring the temperature of gas emerging from a fuel channel, each thermocouple being connected to one contact of a multi-position switch 22 so that the output of any one of them may be used. The primary control term is derived by subtracting the output of one of the thermocouples 18 from a reference voltage derived from potentiometer 34. The reactor is also provided with a neutron flux measuring in chamber 28 and with a flow meter 30 for producing a voltage proportional to the coolant flow in the inlet duct. The voltages produced by these two units are subtracted in unit 29 and differentiated with respect to time to give an additional control term which is fed to amplifier 32. The output of amplifier 32 is used to control the motor which raises or lowers the control rod 15. The rate of change of temperature may be used as the primary control term instead of the temperature itself.
GB23106/59A 1959-07-06 1959-07-06 Improvements in or relating to control apparatus for nuclear reactors Expired GB887392A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB23106/59A GB887392A (en) 1959-07-06 1959-07-06 Improvements in or relating to control apparatus for nuclear reactors

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
GB23106/59A GB887392A (en) 1959-07-06 1959-07-06 Improvements in or relating to control apparatus for nuclear reactors
FR831969A FR1261673A (en) 1960-07-04 1960-07-04 Regulating device for nuclear reactor

Publications (1)

Publication Number Publication Date
GB887392A true GB887392A (en) 1962-01-17

Family

ID=31979928

Family Applications (1)

Application Number Title Priority Date Filing Date
GB23106/59A Expired GB887392A (en) 1959-07-06 1959-07-06 Improvements in or relating to control apparatus for nuclear reactors

Country Status (1)

Country Link
GB (1) GB887392A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3251746A (en) * 1962-10-10 1966-05-17 English Electric Co Ltd Nuclear reactor control means
US3356577A (en) * 1963-09-19 1967-12-05 Sulzer Ag Apparatus for determining the instantaneous output of a nuclear reactor
WO2012035414A3 (en) * 2010-09-17 2012-05-10 Atomic Energy Of Canada Limited Reactor shutdown trip algorithm

Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3251746A (en) * 1962-10-10 1966-05-17 English Electric Co Ltd Nuclear reactor control means
US3356577A (en) * 1963-09-19 1967-12-05 Sulzer Ag Apparatus for determining the instantaneous output of a nuclear reactor
WO2012035414A3 (en) * 2010-09-17 2012-05-10 Atomic Energy Of Canada Limited Reactor shutdown trip algorithm
CN103189926A (en) * 2010-09-17 2013-07-03 加拿大原子能有限公司 Reactor shutdown trip algorithm
CN103189926B (en) * 2010-09-17 2016-04-06 加拿大原子能有限公司 Reactor reactor shut-off system and control method thereof
US9633752B2 (en) 2010-09-17 2017-04-25 Atomic Energy Of Canada Limited Reactor shutdown trip algorithm using derivatives
US9640284B2 (en) 2010-09-17 2017-05-02 Atomic Energy Of Canada Limited Reactor shutdown trip algorithm using derivatives
US9672945B2 (en) 2010-09-17 2017-06-06 Atomic Energy Of Canada Limited Reactor shutdown trip algorithm

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