GB1098623A - Improvements in or relating to liquid moderated nuclear reactors - Google Patents

Improvements in or relating to liquid moderated nuclear reactors

Info

Publication number
GB1098623A
GB1098623A GB25760/63A GB2576063A GB1098623A GB 1098623 A GB1098623 A GB 1098623A GB 25760/63 A GB25760/63 A GB 25760/63A GB 2576063 A GB2576063 A GB 2576063A GB 1098623 A GB1098623 A GB 1098623A
Authority
GB
United Kingdom
Prior art keywords
moderator
pressure
core
density
water
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
GB25760/63A
Inventor
Thomas Deighton
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.)
Babcock International Ltd
Original Assignee
Babcock and Wilcox 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 Babcock and Wilcox Ltd filed Critical Babcock and Wilcox Ltd
Priority to GB25760/63A priority Critical patent/GB1098623A/en
Publication of GB1098623A publication Critical patent/GB1098623A/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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
    • G21C1/322—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core wherein the heat exchanger is disposed above the core
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/005—Flux flattening
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/02—Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/26—Control of nuclear reaction by displacement of the moderator or parts thereof by changing the moderator concentration
    • 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
    • G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
    • 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)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

1,098,623. Reactors. BABCOCK & WILCOX Ltd. Sept. 28, 1964 [June 28, 1963], No. No. 25760/63. Heading G6C. [Also in Division F4] A reactor core comprises fuel, and a liquid moderator at a pressure within a range which is close to but below the thermodynamic critical pressure, and in a condition in which the rate of change of liquid density with pressure is high; the core is operated under simmering conditions, and as the fuel is consumed during operation, the operating pressure is reduced to increase the moderator density, and hence nuclear criticality is maintained. The moderator is preferably light water, which functions as the coolant, and which flows to a steam generating heat exchanger where heat passes from it to a secondary coolant, the steam generator may be located in the reactor pressure vessel. The core is totally immersed in the moderator water, and the small amount of steam generated by the simmering is static in a space above the core and within the pressure vessel. The water pressure is approximately 3200 p.s.i. and its density is about 20 lb./ft.<SP>3</SP> The core is operated in an under-moderated condition, so that a drop in pressure increases the moderator density and results in a higher heat output. The reactor is suitable for ship propulsion in that if the moderator is replaced by sea water following an accident, the excess moderation of sea water at its normal density and temperature renders the core sub-critical. Further control may be obtained with an absorbing type control rod, by varying in the moderator the quantity of additions such as heavy water or boric acid, or soluble poisons which are removed from the moderator as fuel is consumed.
GB25760/63A 1963-06-28 1963-06-28 Improvements in or relating to liquid moderated nuclear reactors Expired GB1098623A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB25760/63A GB1098623A (en) 1963-06-28 1963-06-28 Improvements in or relating to liquid moderated nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB25760/63A GB1098623A (en) 1963-06-28 1963-06-28 Improvements in or relating to liquid moderated nuclear reactors

Publications (1)

Publication Number Publication Date
GB1098623A true GB1098623A (en) 1968-01-10

Family

ID=43569494

Family Applications (1)

Application Number Title Priority Date Filing Date
GB25760/63A Expired GB1098623A (en) 1963-06-28 1963-06-28 Improvements in or relating to liquid moderated nuclear reactors

Country Status (1)

Country Link
GB (1) GB1098623A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0179572A1 (en) * 1984-10-04 1986-04-30 General Atomics Nuclear power system
US4701296A (en) * 1981-12-04 1987-10-20 Framatome & Cie. Fuel array for an undermoderated nuclear reactor

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4701296A (en) * 1981-12-04 1987-10-20 Framatome & Cie. Fuel array for an undermoderated nuclear reactor
EP0179572A1 (en) * 1984-10-04 1986-04-30 General Atomics Nuclear power system
US4863675A (en) * 1984-10-04 1989-09-05 General Atomics Nuclear power system

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