GB931608A - Improvements relating to nuclear reactors - Google Patents

Improvements relating to nuclear reactors

Info

Publication number
GB931608A
GB931608A GB40354/60A GB4035460A GB931608A GB 931608 A GB931608 A GB 931608A GB 40354/60 A GB40354/60 A GB 40354/60A GB 4035460 A GB4035460 A GB 4035460A GB 931608 A GB931608 A GB 931608A
Authority
GB
United Kingdom
Prior art keywords
valves
circuit
valve
coolant
reactor
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
GB40354/60A
Inventor
Frank Marshall
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 GB40354/60A priority Critical patent/GB931608A/en
Publication of GB931608A publication Critical patent/GB931608A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/04—Safety arrangements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/002—Detection of leaks
    • 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
    • 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)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

931,608. Nuclear reactor power plant. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. Nov. 17, 1961 [Nov. 23, 1960], No. 40354/60. Class 39 (4). A heterogeneous nuclear reactor has a number of fluid coolant pressure circuits each with inlet and outlet valves, each circuit being provided, at a point downstream near the outlet valve, with a device sensitive to the flow velocity of the coolant, so that if the flow reaches an abnormally high velocity then the device actuates means to close both valves of the respective circuit. The blower 14 circulates the coolant gas, e.g. CO 2 , through the valve 15, reactor 11, valve 17, exit duct 16 and heatexchanger 12. The devices 18 and 19, which are upstream facing pitot-static tubes, are placed on the entry and exit ducts so that if a breach occurs in the circuit the increased velocity of the gas will be noted by at least one of these tubes and registered by at least one of the differential pressure gauges 21 and 22, which then causes the pointer 24 to bridge a pair of resiliently mounted electrical contacts 25 which causes (a) the closing down of the valves 15 and 17 by means of the outputs 27 and 28; (b) the output 29 to render the other units non-actuable by the connected contact pairs, thus isolating the affected circuit; and (c) the shut down of the reactor over the output 30. The valves may also be operated manually.
GB40354/60A 1960-11-23 1960-11-23 Improvements relating to nuclear reactors Expired GB931608A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB40354/60A GB931608A (en) 1960-11-23 1960-11-23 Improvements relating to nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB40354/60A GB931608A (en) 1960-11-23 1960-11-23 Improvements relating to nuclear reactors

Publications (1)

Publication Number Publication Date
GB931608A true GB931608A (en) 1963-07-17

Family

ID=10414459

Family Applications (1)

Application Number Title Priority Date Filing Date
GB40354/60A Expired GB931608A (en) 1960-11-23 1960-11-23 Improvements relating to nuclear reactors

Country Status (1)

Country Link
GB (1) GB931608A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3341421A (en) * 1963-03-20 1967-09-12 Sulzer Ag Nuclear reactor plant having leak detection control system
JPS5039799B1 (en) * 1969-06-07 1975-12-19

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3341421A (en) * 1963-03-20 1967-09-12 Sulzer Ag Nuclear reactor plant having leak detection control system
JPS5039799B1 (en) * 1969-06-07 1975-12-19

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