FR1392096A - Handling devices for nuclear reactors - Google Patents

Handling devices for nuclear reactors

Info

Publication number
FR1392096A
FR1392096A FR968530A FR968530A FR1392096A FR 1392096 A FR1392096 A FR 1392096A FR 968530 A FR968530 A FR 968530A FR 968530 A FR968530 A FR 968530A FR 1392096 A FR1392096 A FR 1392096A
Authority
FR
France
Prior art keywords
handling devices
nuclear reactors
reactors
nuclear
handling
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
FR968530A
Other languages
French (fr)
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 claimed from GB11796/63A external-priority patent/GB1034866A/en
Application filed by UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to FR968530A priority Critical patent/FR1392096A/en
Application granted granted Critical
Publication of FR1392096A publication Critical patent/FR1392096A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • G21C1/00—Reactor types
    • G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • G21C1/028—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders cooled by a pressurised coolant
    • 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
    • G21C1/10—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 moderator and coolant being different or separated
    • G21C1/12—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 moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor or gas-graphite 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
    • G21C13/02—Details
    • G21C13/04—Arrangements for expansion and contraction
    • 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
    • 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
    • G21C19/16—Articulated or telescopic chutes or tubes for connection to channels in the reactor core
    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • 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
    • G21C1/086—Pressurised water reactors
    • 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
FR968530A 1963-03-25 1964-03-24 Handling devices for nuclear reactors Expired FR1392096A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
FR968530A FR1392096A (en) 1963-03-25 1964-03-24 Handling devices for nuclear reactors

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
GB11796/63A GB1034866A (en) 1963-03-25 1963-03-25 Improvements in or relating to manipulating devices for use in nuclear reactors
FR968530A FR1392096A (en) 1963-03-25 1964-03-24 Handling devices for nuclear reactors

Publications (1)

Publication Number Publication Date
FR1392096A true FR1392096A (en) 1965-03-12

Family

ID=26206634

Family Applications (1)

Application Number Title Priority Date Filing Date
FR968530A Expired FR1392096A (en) 1963-03-25 1964-03-24 Handling devices for nuclear reactors

Country Status (1)

Country Link
FR (1) FR1392096A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0146804A2 (en) * 1983-12-21 1985-07-03 Westinghouse Electric Corporation Fuel assembly peripheral rod lifting device
US4696784A (en) * 1984-03-28 1987-09-29 Westinghouse Electric Corp. System for manipulating radioactive fuel rods within a nuclear fuel assembly

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0146804A2 (en) * 1983-12-21 1985-07-03 Westinghouse Electric Corporation Fuel assembly peripheral rod lifting device
EP0146804A3 (en) * 1983-12-21 1985-12-18 Westinghouse Electric Corporation Fuel assembly peripheral rod lifting device
US4696784A (en) * 1984-03-28 1987-09-29 Westinghouse Electric Corp. System for manipulating radioactive fuel rods within a nuclear fuel assembly

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