GB981424A - Improvements in or relating to heterogeneous nuclear reactors - Google Patents

Improvements in or relating to heterogeneous nuclear reactors

Info

Publication number
GB981424A
GB981424A GB24720/60A GB2472060A GB981424A GB 981424 A GB981424 A GB 981424A GB 24720/60 A GB24720/60 A GB 24720/60A GB 2472060 A GB2472060 A GB 2472060A GB 981424 A GB981424 A GB 981424A
Authority
GB
United Kingdom
Prior art keywords
tube
tubes
water
flow
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
GB24720/60A
Inventor
Stanley Hackney
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
Priority to NL288037D priority Critical patent/NL288037A/xx
Priority to BE627360D priority patent/BE627360A/xx
Application filed by UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to GB24720/60A priority patent/GB981424A/en
Priority to DEU8168A priority patent/DE1202404B/en
Priority to FR867663A priority patent/FR1294664A/en
Priority to GB2334/62A priority patent/GB1003826A/en
Priority to US238438A priority patent/US3212985A/en
Priority to US238446A priority patent/US3175954A/en
Priority to FR922104A priority patent/FR1344149A/en
Publication of GB981424A publication Critical patent/GB981424A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/04—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material
    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/08—Vessels characterised by the material; Selection of materials for pressure vessels
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/08—Vessels characterised by the material; Selection of materials for pressure vessels
    • G21C13/087—Metallic vessels
    • 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
    • G21C1/09—Pressure regulating arrangements, i.e. pressurisers
    • 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)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)

Abstract

981,424. Nuclear reactors. UNITED KING- DOM ATOMIC ENERGY AUTHORITY. June 16, 1961 [July 15, 1960], No. 24720/60. Heading G6C. A heterogenous nuclear reactor core comprises tubes 15 containing sheathed fuel elements 16 disposed in a heat transfer fluid, and being interconnected so that, in relation to a cooling fluid passed over the tubes 15, the heat transfer fluid proceeds first in one tube 33 in the same direction as the cooling fluid and then in an adjacent tube 35 in the opposite direction, the tubes being so constructed that heat transfer between the two fluids is reduced when they flew in the same direction and increased when they flow in opposite directions. The invention is described with reference to a boiling water reactor and, as shown in the section in Fig. 2, pressurized water is circulated up one tube 33 between the fuel elements 16, in a direction parallel to that of the flow of a water coolant/moderater outside the tubes 15, into the portion of the tube 33 above the fuel elements 16 which contains a heat insulator 34. This is preferably a thin sleeve supported with clearance within the tube 33, the annular space between it and the tube being closed at one end and containing stationary water. The pressurised water then flows through a coupling 20 to the tube 35, the upper portion of which has longitudinal fins 36 on its outer surface and contains a plug 37 to increase the flow velocity of the water. The upper ends of the tubes 15 are provided, above the water level in the reactor pressure vessel, with spaced circumferential fins 32, those of one tube interlacing with those of adjacent tubes so as to serve as a steam separator. The circulating pressurised water loses little heat in the tube 33 but, over the longitudinally finned length of the tube 35 where a counter-flow relationship exists between the pressurized water inside the tube and the steam from the reactor coolant/ moderater, the pressurized water superheats the steam to a temperature near that which it itself attains. Since only half the tubes 15 are effective for superheating purposes, the flow of steam may be given a cross-flow component by means of a frusto-conical baffle plate situated above the separator section and differential heat transfer arrangement shown in Fig. 2. Each of the tubes 15 contains a group of juxtaposed sheathed fuel elements of circular cross-section, there being three, viz. 28, 29 and 30, in the illustrated example (Fig. 3). Wound round the sheath of each element is a helical spacing wire 41 of such a diameter that the three elements fit snugly in a triangularly arranged bundle in the tube, one element being inserted with the wire helix oppositely handed to the other two. Specification 981,423 is referred to.
GB24720/60A 1960-07-15 1960-07-15 Improvements in or relating to heterogeneous nuclear reactors Expired GB981424A (en)

Priority Applications (9)

Application Number Priority Date Filing Date Title
NL288037D NL288037A (en) 1960-07-15
BE627360D BE627360A (en) 1960-07-15
GB24720/60A GB981424A (en) 1960-07-15 1960-07-15 Improvements in or relating to heterogeneous nuclear reactors
DEU8168A DE1202404B (en) 1960-07-15 1961-07-10 Boiling water reactor core with vertically arranged pipes combined in pairs, in which the fuel assemblies are located
FR867663A FR1294664A (en) 1960-07-15 1961-07-11 Heterogeneous nuclear reactors
GB2334/62A GB1003826A (en) 1960-07-15 1962-01-22 Improvements in or relating to nuclear reactors
US238438A US3212985A (en) 1960-07-15 1962-11-19 Boiling water nuclear reactor operating with primary and secondary coolant
US238446A US3175954A (en) 1960-07-15 1962-11-19 Nuclear reactor core structure
FR922104A FR1344149A (en) 1960-07-15 1963-01-21 Nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB24720/60A GB981424A (en) 1960-07-15 1960-07-15 Improvements in or relating to heterogeneous nuclear reactors

Publications (1)

Publication Number Publication Date
GB981424A true GB981424A (en) 1965-01-27

Family

ID=10216187

Family Applications (1)

Application Number Title Priority Date Filing Date
GB24720/60A Expired GB981424A (en) 1960-07-15 1960-07-15 Improvements in or relating to heterogeneous nuclear reactors

Country Status (1)

Country Link
GB (1) GB981424A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN113345609A (en) * 2021-06-02 2021-09-03 哈尔滨工程大学 External cooling system for pressure vessel of floating nuclear power station

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN113345609A (en) * 2021-06-02 2021-09-03 哈尔滨工程大学 External cooling system for pressure vessel of floating nuclear power station
CN113345609B (en) * 2021-06-02 2022-03-01 哈尔滨工程大学 External cooling system for pressure vessel of floating nuclear power station

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