GB817265A - Improvements in or relating to nuclear reactors - Google Patents

Improvements in or relating to nuclear reactors

Info

Publication number
GB817265A
GB817265A GB26526/57A GB2652657A GB817265A GB 817265 A GB817265 A GB 817265A GB 26526/57 A GB26526/57 A GB 26526/57A GB 2652657 A GB2652657 A GB 2652657A GB 817265 A GB817265 A GB 817265A
Authority
GB
United Kingdom
Prior art keywords
fuel
core
tubes
test
tank
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
GB26526/57A
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.)
Westinghouse Electric International Co
Original Assignee
Westinghouse Electric International Co
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 Westinghouse Electric International Co filed Critical Westinghouse Electric International Co
Publication of GB817265A publication Critical patent/GB817265A/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
    • G21C1/00—Reactor types
    • G21C1/30—Subcritical reactors ; Experimental reactors other than swimming-pool reactors or zero-energy reactors
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/30—Subcritical reactors ; Experimental reactors other than swimming-pool reactors or zero-energy reactors
    • G21C1/303—Experimental or irradiation arrangements inside the reactor
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/02—Details of handling arrangements
    • G21C19/10—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
    • G21C19/105—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements with grasping or spreading coupling elements
    • 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
    • G21C3/36—Assemblies of plate-shaped fuel elements or coaxial tubes
    • 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
    • G21C7/10—Construction of control 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)
  • Testing Resistance To Weather, Investigating Materials By Mechanical Methods (AREA)

Abstract

817,265. Nuclear reactors. WESTING- HOUSE ELECTRIC INTERNATIONAL CO. Aug. 22, 1957 [Sept. 19, 1956], No. 26526/57. Drawings to Specification. Class 39(4). In a pressurised water reactor, materials may be tested in the core under controlled conditions of temperature and pressure. The core coolant, light water, is separate from the moderator, heavy water. The core comprises a steel tank having a series of internal vertical tubes in which are inserted the fuel elements, control rods and test specimens. The cooling water passes round the outside of the tank and through the core down the tubes containing the fuel and control elements. The moderating water flows through the inside of the tank between the fuel control element and test specimen tubes. Some test specimens are mounted in containers which are inserted into the vertical tubes from the underside of the core and which may be subjected internally to a flow of pressurized fluid and which are provided with electric test leads. Other test samples are held in sealed containers inserted into the vertical tubes. The control rods are releasable magnetically in an emergency and when withdrawn upwardly out of the core a fuel element is simultaneously drawn into the space to reduce disturbances of the neutron flux. Each fuel element consists of three concentric, spaced aluminium tubes, the fuel metal being bonded to the centre section of each tube. The materials employed are, shield, concrete and magnetite; fuel, uraniumaluminium, alloy ; control rods, cadmium.
GB26526/57A 1956-09-19 1957-08-22 Improvements in or relating to nuclear reactors Expired GB817265A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US817265XA 1956-09-19 1956-09-19

Publications (1)

Publication Number Publication Date
GB817265A true GB817265A (en) 1959-07-29

Family

ID=22165995

Family Applications (1)

Application Number Title Priority Date Filing Date
GB26526/57A Expired GB817265A (en) 1956-09-19 1957-08-22 Improvements in or relating to nuclear reactors

Country Status (3)

Country Link
BE (1) BE560958A (en)
FR (1) FR1187050A (en)
GB (1) GB817265A (en)

Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1125561B (en) * 1959-11-24 1962-03-15 Siemens Ag Cooling pipe for a heterogeneous nuclear reactor
US3128234A (en) * 1960-08-26 1964-04-07 Jr Joseph F Cage Modular core units for a neutronic reactor
US3163583A (en) * 1960-09-06 1964-12-29 Westinghouse Electric Corp Fuel follower for a heterogeneous nuclear reactor
US3208914A (en) * 1961-01-05 1965-09-28 Allis Chalmers Mfg Co Nuclear reactor with improved core arrangement facilitating loading and unloading of fuel assemblies and control rod assemblies
US3280005A (en) * 1962-09-06 1966-10-18 Belgian Organization Ct D Etud Fuel element for experimental nuclear reactors
US3318776A (en) * 1960-12-23 1967-05-09 American Mach & Foundry Two pass pressure tube research reactor
US3318777A (en) * 1960-01-07 1967-05-09 American Mach & Foundry Cooling process for fuel elements of a nuclear reactor of the swimming-pool type and nuclear reactor according to this process
CN103821757A (en) * 2014-02-21 2014-05-28 清华大学 Dynamic pressure and static pressure mechanical seal combined type nuclear main pump gland seal system with parking sealing component
CN113871041A (en) * 2021-09-26 2021-12-31 中国原子能科学研究院 Control rod assembly mounting method, control rod assembly removing method and control rod assembly replacing method

Cited By (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1125561B (en) * 1959-11-24 1962-03-15 Siemens Ag Cooling pipe for a heterogeneous nuclear reactor
US3318777A (en) * 1960-01-07 1967-05-09 American Mach & Foundry Cooling process for fuel elements of a nuclear reactor of the swimming-pool type and nuclear reactor according to this process
US3128234A (en) * 1960-08-26 1964-04-07 Jr Joseph F Cage Modular core units for a neutronic reactor
US3163583A (en) * 1960-09-06 1964-12-29 Westinghouse Electric Corp Fuel follower for a heterogeneous nuclear reactor
US3318776A (en) * 1960-12-23 1967-05-09 American Mach & Foundry Two pass pressure tube research reactor
US3208914A (en) * 1961-01-05 1965-09-28 Allis Chalmers Mfg Co Nuclear reactor with improved core arrangement facilitating loading and unloading of fuel assemblies and control rod assemblies
US3280005A (en) * 1962-09-06 1966-10-18 Belgian Organization Ct D Etud Fuel element for experimental nuclear reactors
CN103821757A (en) * 2014-02-21 2014-05-28 清华大学 Dynamic pressure and static pressure mechanical seal combined type nuclear main pump gland seal system with parking sealing component
CN103821757B (en) * 2014-02-21 2016-02-24 清华大学 There is the active and static pressure mechanical seal combined nuclear main pump gland seal system of parking sealer
CN113871041A (en) * 2021-09-26 2021-12-31 中国原子能科学研究院 Control rod assembly mounting method, control rod assembly removing method and control rod assembly replacing method
CN113871041B (en) * 2021-09-26 2024-05-10 中国原子能科学研究院 Method for installing, removing and replacing control rod assembly

Also Published As

Publication number Publication date
FR1187050A (en) 1959-09-04
BE560958A (en) 1900-01-01

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