NL249664A - - Google Patents

Info

Publication number
NL249664A
NL249664A NL249664DA NL249664A NL 249664 A NL249664 A NL 249664A NL 249664D A NL249664D A NL 249664DA NL 249664 A NL249664 A NL 249664A
Authority
NL
Netherlands
Application number
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.)
Publication date
Publication of NL249664A publication Critical patent/NL249664A/xx

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
    • 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
    • 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
    • G21C19/18—Apparatus for bringing fuel elements to the reactor charge area, e.g. from a storage place
    • 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
    • G21C19/32—Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage place; Apparatus for handling radioactive objects or materials within a storage place or removing them therefrom
    • 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
NL249664D 1960-03-04 NL249664A (xx)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CH247760A CH377007A (de) 1960-03-04 1960-03-04 Verfahren zum Auswechseln von stabförmigen Brennstoffelementen in einem Atomreaktor und Reaktor zur Ausübung des Verfahrens

Publications (1)

Publication Number Publication Date
NL249664A true NL249664A (xx) 1900-01-01

Family

ID=4234669

Family Applications (2)

Application Number Title Priority Date Filing Date
NL249664D NL249664A (xx) 1960-03-04
NL113287D NL113287C (xx) 1960-03-04

Family Applications After (1)

Application Number Title Priority Date Filing Date
NL113287D NL113287C (xx) 1960-03-04

Country Status (6)

Country Link
US (1) US3206366A (xx)
BE (1) BE600832A (xx)
CH (1) CH377007A (xx)
DE (1) DE1292263B (xx)
GB (1) GB943118A (xx)
NL (2) NL113287C (xx)

Families Citing this family (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3637096A (en) * 1969-02-27 1972-01-25 Combustion Eng Nuclear fuel transfer machine
US3755079A (en) * 1969-12-12 1973-08-28 Atomic Energy Commission Nuclear reactor plant with integral entombment
US4058224A (en) * 1973-10-23 1977-11-15 The Babcock & Wilcox Company Traversing and vertically swinging strongback
FR2405540A1 (fr) * 1977-10-04 1979-05-04 Framatome Sa Installation de centrale nucleaire a piscines decalees
US4717531A (en) * 1983-09-23 1988-01-05 Westinghouse Electric Corp. Fuel transfer system upender using translation drive
US4749541A (en) * 1986-12-05 1988-06-07 Westinghouse Electric Corp. Position sensing mechanism for a nuclear fuel transfer system
US4968477A (en) * 1989-02-02 1990-11-06 Westinghouse Electric Corp. Method and apparatus for removing the fuel rods of a nuclear fuel assembly
US11079054B2 (en) * 2015-06-23 2021-08-03 Atomic Energy Of Canada Limited Cross-over fluid coupling

Family Cites Families (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2778792A (en) * 1946-04-19 1957-01-22 Szilard Leo Method for unloading reactors
US2915446A (en) * 1954-11-29 1959-12-01 Asea Ab Gas cooled nuclear reactor
US2987458A (en) * 1954-12-14 1961-06-06 Calvin R Breden Twisted ribbon fuel element
NL103807C (xx) * 1955-07-27
GB842329A (en) * 1955-12-08 1960-07-27 Rolls Royce Improvements in or relating to nuclear reactors
DE1064161B (de) * 1956-07-10 1959-08-27 Babcock & Wilcox Dampfkessel Vorrichtung zum Abstuetzen von Brennstoffkoerpern in den Brennstoffschaechten eines Reaktors
BE560765A (xx) * 1956-09-12
DE1055141B (de) * 1957-01-10 1959-04-16 Asea Ab Brennstoffelement fuer heterogenen Kernreaktor
US2994656A (en) * 1958-12-31 1961-08-01 Zumwalt Lloyd Robert Fuel element construction

Also Published As

Publication number Publication date
BE600832A (fr) 1961-09-04
NL113287C (xx) 1900-01-01
US3206366A (en) 1965-09-14
GB943118A (en) 1963-11-27
DE1292263B (de) 1969-04-10
CH377007A (de) 1964-04-30

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