GB1236578A - Nuclear reactor installations - Google Patents

Nuclear reactor installations

Info

Publication number
GB1236578A
GB1236578A GB54370/67A GB5437067A GB1236578A GB 1236578 A GB1236578 A GB 1236578A GB 54370/67 A GB54370/67 A GB 54370/67A GB 5437067 A GB5437067 A GB 5437067A GB 1236578 A GB1236578 A GB 1236578A
Authority
GB
United Kingdom
Prior art keywords
core
nov
pressure vessel
coolant circuit
moderator
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
GB54370/67A
Inventor
Douglas Roy Ebeling
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 GB54370/67A priority Critical patent/GB1236578A/en
Publication of GB1236578A publication Critical patent/GB1236578A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation 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
    • 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
    • G21C1/14—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
    • G21C1/16—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor
    • G21C1/18—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised
    • G21C1/20—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
    • 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)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

1,236,578. Cooling reactors. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. 14 Nov., 1968 [29 Nov., 1967], No. 54370/67. Heading G6C. The reactor core 1 is cooled by the circulation of boiling water upwards through the vertical fuel tubes 4 mounted within a heavy water moderator contained in a Calandria tank. The coolant circuit 2 and core 1 are mounted within the concrete pressure vessel 3 which has an atmosphere of pressurized carbon dioxide gas. The gas and water pressures are substantially the same and thus a large fracture of the coolant circuit is unlikely. Depressurization of the pressure vessel causes ejection of plugs from the Calandria and the flashing off of steam from the moderator thereby reducing moderation and core reactivity.
GB54370/67A 1967-11-29 1967-11-29 Nuclear reactor installations Expired GB1236578A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB54370/67A GB1236578A (en) 1967-11-29 1967-11-29 Nuclear reactor installations

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB54370/67A GB1236578A (en) 1967-11-29 1967-11-29 Nuclear reactor installations

Publications (1)

Publication Number Publication Date
GB1236578A true GB1236578A (en) 1971-06-23

Family

ID=10470784

Family Applications (1)

Application Number Title Priority Date Filing Date
GB54370/67A Expired GB1236578A (en) 1967-11-29 1967-11-29 Nuclear reactor installations

Country Status (1)

Country Link
GB (1) GB1236578A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4986956A (en) * 1989-11-27 1991-01-22 Stone & Webster Engineering Corporation Passive nuclear power plant containment system

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4986956A (en) * 1989-11-27 1991-01-22 Stone & Webster Engineering Corporation Passive nuclear power plant containment system

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