BE637010A - - Google Patents

Info

Publication number
BE637010A
BE637010A BE637010DA BE637010A BE 637010 A BE637010 A BE 637010A BE 637010D A BE637010D A BE 637010DA BE 637010 A BE637010 A BE 637010A
Authority
BE
Belgium
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 BE637010A publication Critical patent/BE637010A/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
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F9/00—Casings; Header boxes; Auxiliary supports for elements; Auxiliary members within casings
    • F28F9/007—Auxiliary supports for elements
    • F28F9/013—Auxiliary supports for elements for tubes or tube-assemblies
    • F28F9/0135—Auxiliary supports for elements for tubes or tube-assemblies formed by grids having only one tube per closed grid opening
    • 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
    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/02—Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect
    • G21C7/04—Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect of burnable poisons
    • 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

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
BE637010D 1962-09-05 BE637010A (fr)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB34103/62A GB998624A (en) 1962-09-05 1962-09-05 Improvements relating to nuclear reactor fuel element assemblies

Publications (1)

Publication Number Publication Date
BE637010A true BE637010A (fr) 1900-01-01

Family

ID=10361416

Family Applications (2)

Application Number Title Priority Date Filing Date
BE637010D BE637010A (fr) 1962-09-05
BE637009D BE637009A (fr) 1962-09-05

Family Applications After (1)

Application Number Title Priority Date Filing Date
BE637009D BE637009A (fr) 1962-09-05

Country Status (4)

Country Link
US (1) US3297540A (fr)
BE (2) BE637009A (fr)
GB (2) GB998624A (fr)
NL (2) NL297401A (fr)

Families Citing this family (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
IL31530A (en) * 1968-02-26 1973-03-30 Gen Electric A fuel core embodying means for reactivity and power distribution control of nuclear reactor
US3984284A (en) * 1973-08-03 1976-10-05 Exxon Nuclear Company, Inc. Spacer capture system for nuclear fuel assemblies
DE2348947C3 (de) * 1973-09-28 1979-10-31 Kraftwerk Union Ag, 4330 Muelheim Brennelement für gasgekühlte Kernreaktoren
US4189348A (en) * 1976-07-26 1980-02-19 General Atomic Company Fuel rod assembly to manifold attachment
US4235673A (en) * 1978-01-12 1980-11-25 Combustion Engineering, Inc. Chip sleeve for nuclear fuel elements
US20050135547A1 (en) * 1998-03-11 2005-06-23 Wolfgang Schulz Control element for a nuclear reactor
DE10146128B4 (de) * 2001-09-19 2005-03-03 Framatome Anp Gmbh Brennelement für einen Druckwasserreaktor
US8638901B2 (en) * 2010-12-29 2014-01-28 Westinghouse Electric Company Llc Optimum configuration for fast reactors
CN106927703B (zh) * 2017-04-19 2019-07-09 北新集团建材股份有限公司 一种煅烧窑管道支撑系统

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2806820A (en) * 1947-08-18 1957-09-17 Eugene P Wigner Neutronic reactor
BE567472A (fr) * 1957-05-14
US3049484A (en) * 1957-10-31 1962-08-14 Curtiss Wright Corp Apparatus for production of radioactive isotopes
US3105026A (en) * 1958-08-26 1963-09-24 James J Dickson Fuel elment for nuclear reactors
US2984613A (en) * 1959-04-09 1961-05-16 Charles H Bassett Fuel element for nuclear reactors
BE620998A (fr) * 1961-08-02 1900-01-01

Also Published As

Publication number Publication date
GB998625A (en) 1965-07-14
GB998624A (en) 1965-07-14
US3297540A (en) 1967-01-10
NL297401A (fr) 1900-01-01
BE637009A (fr) 1900-01-01
NL297402A (fr) 1900-01-01

Similar Documents

Publication Publication Date Title
AT2636B (fr)
AT13493B (fr)
AT11620B (fr)
AT12463B (fr)
AT13369B (fr)
AT2799B (fr)
AT2567B (fr)
AT5013B (fr)
AT10960B (fr)
AT13580B (fr)
AT14149B (fr)
AT11731B (fr)
AT4871B (fr)
AT11927B (fr)
AT12024B (fr)
AT12220B (fr)
AT12609B (fr)
AT12720B (fr)
AT12855B (fr)
AT12875B (fr)
AT13070B (fr)
AT11575B (fr)
AT13314B (fr)
AT13516B (fr)
AT11478B (fr)