GB880455A - Improvements in or relating to nuclear reactor installations - Google Patents

Improvements in or relating to nuclear reactor installations

Info

Publication number
GB880455A
GB880455A GB19147/59A GB1914759A GB880455A GB 880455 A GB880455 A GB 880455A GB 19147/59 A GB19147/59 A GB 19147/59A GB 1914759 A GB1914759 A GB 1914759A GB 880455 A GB880455 A GB 880455A
Authority
GB
United Kingdom
Prior art keywords
tubes
core
passing
feed water
steam
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
GB19147/59A
Inventor
Norman Bradley
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 GB19147/59A priority Critical patent/GB880455A/en
Publication of GB880455A publication Critical patent/GB880455A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • G21C1/082—Reactors where the coolant is overheated
    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/04—Reactor and engine not structurally combined
    • G21D5/08—Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
    • 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)
  • Physical Or Chemical Processes And Apparatus (AREA)

Abstract

880,455. Nuclear reactors. UNITED KING DOM ATOMIC ENERGY AUTHORITY. May 20, 1960 [June 4, 1959], No. 19147/59. Class 39 (4) [Also in Group XIII] A nuclear reactor has means for circulating D 2 O through one part of the core, in tubes 2, means for passing feed water, which may be H 2 O, in heat exchange with the D 2 O to raise saturated steam from the feed water, at 4, and means for passing this steam through a second part of the core, in tubes 5, to receive superheat. The fuel in tubes 2 is UO 2 of moderate enrichment clad in Zr, that in tubes 5 is UO 2 of higher enrichment clad in stainless steel. The D 2 O is arranged to circulate by convection if pumps fail. The Provisional Specification describes a reactor with means of passing feed water through one part of the core to raise saturated steam and means for passing this steam through another part of the core to receive superheat.
GB19147/59A 1959-06-04 1959-06-04 Improvements in or relating to nuclear reactor installations Expired GB880455A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB19147/59A GB880455A (en) 1959-06-04 1959-06-04 Improvements in or relating to nuclear reactor installations

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB19147/59A GB880455A (en) 1959-06-04 1959-06-04 Improvements in or relating to nuclear reactor installations

Publications (1)

Publication Number Publication Date
GB880455A true GB880455A (en) 1961-10-25

Family

ID=10124529

Family Applications (1)

Application Number Title Priority Date Filing Date
GB19147/59A Expired GB880455A (en) 1959-06-04 1959-06-04 Improvements in or relating to nuclear reactor installations

Country Status (1)

Country Link
GB (1) GB880455A (en)

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