GB1086060A - Improvements in or relating to nuclear reactors - Google Patents

Improvements in or relating to nuclear reactors

Info

Publication number
GB1086060A
GB1086060A GB47442/63A GB4744263A GB1086060A GB 1086060 A GB1086060 A GB 1086060A GB 47442/63 A GB47442/63 A GB 47442/63A GB 4744263 A GB4744263 A GB 4744263A GB 1086060 A GB1086060 A GB 1086060A
Authority
GB
United Kingdom
Prior art keywords
coolant
fuel rod
emergency
spray
assembly
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
GB47442/63A
Inventor
Dennis Ross Poulter
John Joseph Campbell
Raymond Reginald Cranfield
George Lister Shires
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 GB47442/63A priority Critical patent/GB1086060A/en
Priority to FR996851A priority patent/FR1417483A/en
Priority to ES0306610A priority patent/ES306610A1/en
Priority to GB32379/65A priority patent/GB1112346A/en
Priority to GB38241/65A priority patent/GB1131307A/en
Priority to US565764A priority patent/US3346459A/en
Priority to BE684620D priority patent/BE684620A/xx
Priority to FR70886A priority patent/FR90327E/en
Priority to FR75236A priority patent/FR91128E/en
Publication of GB1086060A publication Critical patent/GB1086060A/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
    • G21C1/14—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
    • G21C13/02—Details
    • G21C13/06—Sealing-plugs
    • G21C13/067—Sealing-plugs for tubes, e.g. standpipes; Locking devices for plugs
    • 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
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/108—Measuring reactor flux
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/33—Supporting or hanging of elements in the bundle; Means forming part of the bundle for inserting it into, or removing it from, the core; Means for coupling adjacent bundles
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/34—Spacer grids
    • G21C3/348—Spacer grids formed of assembled non-intersecting strips
    • 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
    • G21C7/08—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 by displacement of solid control elements, e.g. control rods
    • G21C7/20—Disposition of shock-absorbing devices ; Braking arrangements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • 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

1,086,060. Reactors. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. Nov. 24, 1964 [Dec. 2, 1963], No. 47442/63. Heading G6C. A nuclear reactor in which a bulk moderator is penetrated by a number of pressure tubes housing fuel rod assemblies in contact with operating coolant flowing within the tube, characterized in that conduits connect a source of emergency coolant with sprays mounted within the fuel rod assemblies; a fluid flow control valve is actuated in response to an emergency signal (arising, e.g. from major break in primary coolant circuit) so as to spray the fuel rod assemblies to prevent damage by accumulations of fission product decay heat. A centrally disposed closed end tube is disposed in each fuel rod assembly and includes radially extending spray orifices distributed about its length; its upper open end is attached by conduit 8 to a supply line 10 passing, via the flow control valve 28, to a nitrogen pressurized water tank 9. The time elapsed during emptying of tank 9 following an emergency, is sufficient to ensure that the reactor containment vessel will be at atmospheric pressure when it is emptied. Further emergency coolant is then available using gravity flow from a secondary tank 25, after shutting Valve 28 and opening valve 27. Orifice plates 33 ensure equal emergency coolant supply to each spray tube. Some of the water supplied to the spray tubes may be directed adjacent to each fuel rod assembly and sprayed radially against deflector plates at the assembly top ends, so that the coolant is directed downwards on to the outermost concentric circle of fuel rods in each assembly.
GB47442/63A 1963-12-02 1963-12-02 Improvements in or relating to nuclear reactors Expired GB1086060A (en)

Priority Applications (9)

Application Number Priority Date Filing Date Title
GB47442/63A GB1086060A (en) 1963-12-02 1963-12-02 Improvements in or relating to nuclear reactors
FR996851A FR1417483A (en) 1963-12-02 1964-11-30 Nuclear reactor
ES0306610A ES306610A1 (en) 1963-12-02 1964-12-01 Improvements in or relating to nuclear reactors
GB32379/65A GB1112346A (en) 1963-12-02 1965-07-28 Improvements relating to nuclear reactors
GB38241/65A GB1131307A (en) 1963-12-02 1965-09-07 Nuclear reactors
US565764A US3346459A (en) 1963-12-02 1966-07-18 Nuclear reactors
BE684620D BE684620A (en) 1963-12-02 1966-07-26
FR70886A FR90327E (en) 1963-12-02 1966-07-26 Nuclear reactor
FR75236A FR91128E (en) 1963-12-02 1966-09-05 Nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB47442/63A GB1086060A (en) 1963-12-02 1963-12-02 Improvements in or relating to nuclear reactors

Publications (1)

Publication Number Publication Date
GB1086060A true GB1086060A (en) 1967-10-04

Family

ID=38571458

Family Applications (1)

Application Number Title Priority Date Filing Date
GB47442/63A Expired GB1086060A (en) 1963-12-02 1963-12-02 Improvements in or relating to nuclear reactors

Country Status (3)

Country Link
ES (1) ES306610A1 (en)
FR (1) FR1417483A (en)
GB (1) GB1086060A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3528884A (en) * 1967-09-28 1970-09-15 Westinghouse Electric Corp Safety cooling system for a nuclear reactor
CN109478429A (en) * 2016-05-04 2019-03-15 水利矿业核能公司 Nuclear reactor with the fuel element for being equipped with cooling pipe

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2323378A1 (en) * 1972-06-02 1973-12-13 Westinghouse Electric Corp EMERGENCY COOLING SYSTEM FOR A NUCLEAR REACTOR

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3528884A (en) * 1967-09-28 1970-09-15 Westinghouse Electric Corp Safety cooling system for a nuclear reactor
CN109478429A (en) * 2016-05-04 2019-03-15 水利矿业核能公司 Nuclear reactor with the fuel element for being equipped with cooling pipe

Also Published As

Publication number Publication date
ES306610A1 (en) 1965-12-16
FR1417483A (en) 1965-11-12

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