GB992021A - Improvements in nuclear reactors - Google Patents

Improvements in nuclear reactors

Info

Publication number
GB992021A
GB992021A GB39775/61A GB3977561A GB992021A GB 992021 A GB992021 A GB 992021A GB 39775/61 A GB39775/61 A GB 39775/61A GB 3977561 A GB3977561 A GB 3977561A GB 992021 A GB992021 A GB 992021A
Authority
GB
United Kingdom
Prior art keywords
coolant
magazine
compartment
fed
pressure
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
GB39775/61A
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
Publication of GB992021A publication Critical patent/GB992021A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/04Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/336Spacer elements for fuel rods in the bundle
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Abstract

992, 021. Reactors. BABCOCK & WILCOX Ltd. Nov. 7, 1961 [Nov. 8, 1960], No. 39775/61. Heading G6C. A nuclear reactor includes magazines containing bundles of fuel pins spaced from one another and the magazine wall by spacing means, and each magazine wall, which forms externally part of a pressure compartment, is constructed of thin metallic sheeting made flexible by flutes or corrugations so that a fluid pressure differential maintained between the compartment and a coolant flowing through the magazine serves to pack the spacing means tightly between and around the fuel pins. The flutes or corrugations 23 are also used to space the magazines apart. The spacers 28A, 28B and 28C (Fig. 3) which space the fuel pins 25 from one another and from the magazine walls 22, comprise short annular cylindrical rollers of identical length but different diameters, and are arranged in vertically spaced horizontal layers throughout the magazine 13. Each fuel pin is shouldered at its ends 26 for the rollers to rest on. The coolant is heated in the magazine 13, passed through a turbine, heat exchanger and pump respectively, and then recirculated through the magazine. The pressure compartment, which is contained in a pressure vessel, is pressurized by coolant fed through an opening in the pressure vessel from a point downstream of the pump. In Fig. 4 the coolant is not fed into the compartment 20 through the vessel, but is fed through a conduit 31. The conduit 31 has a flared mouth 32 adjacent a nozzle restriction 33 which causes high velocity coolant to enter the mouth 32 resulting in a pressure build-up within the conduit 31 which is transmitted to the coolant within the compartment 20. The pressurising conduits need not be supplied from the reactor coolant supply, but from special booster pumps which normally supply new coolant to the circuit. The new coolant can be fed to the compartment from which an overflow can open into the main coolant circuit.
GB39775/61A 1960-11-08 1961-11-07 Improvements in nuclear reactors Expired GB992021A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DED0034689 1960-11-08

Publications (1)

Publication Number Publication Date
GB992021A true GB992021A (en) 1965-05-12

Family

ID=7042291

Family Applications (1)

Application Number Title Priority Date Filing Date
GB39775/61A Expired GB992021A (en) 1960-11-08 1961-11-07 Improvements in nuclear reactors

Country Status (1)

Country Link
GB (1) GB992021A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4021300A (en) * 1975-05-23 1977-05-03 The United States Of America As Represented By The United States Energy Research And Development Administration Improved nuclear fuel assembly grid spacer
US4666664A (en) * 1982-04-15 1987-05-19 Westinghouse Electric Corp. Coolant flow paths within a nuclear fuel assembly
US4897241A (en) * 1981-11-30 1990-01-30 Combustion Engineering, Inc. Anti-bow grid for nuclear fuel assembly
US6347130B1 (en) * 1994-12-23 2002-02-12 Westinghouse Atom Ab Fuel assembly with short fuel units

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4021300A (en) * 1975-05-23 1977-05-03 The United States Of America As Represented By The United States Energy Research And Development Administration Improved nuclear fuel assembly grid spacer
US4897241A (en) * 1981-11-30 1990-01-30 Combustion Engineering, Inc. Anti-bow grid for nuclear fuel assembly
US4666664A (en) * 1982-04-15 1987-05-19 Westinghouse Electric Corp. Coolant flow paths within a nuclear fuel assembly
US6347130B1 (en) * 1994-12-23 2002-02-12 Westinghouse Atom Ab Fuel assembly with short fuel units

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