GB1431475A - Nuclear reactor fuel elements - Google Patents

Nuclear reactor fuel elements

Info

Publication number
GB1431475A
GB1431475A GB4404273A GB4404273A GB1431475A GB 1431475 A GB1431475 A GB 1431475A GB 4404273 A GB4404273 A GB 4404273A GB 4404273 A GB4404273 A GB 4404273A GB 1431475 A GB1431475 A GB 1431475A
Authority
GB
United Kingdom
Prior art keywords
zone
webs
rods
contain
flow
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
GB4404273A
Other languages
English (en)
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.)
Interatom Internationale Atomreaktorbau GmbH
Original Assignee
Interatom Internationale Atomreaktorbau GmbH
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 Interatom Internationale Atomreaktorbau GmbH filed Critical Interatom Internationale Atomreaktorbau GmbH
Publication of GB1431475A publication Critical patent/GB1431475A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • G21C1/022—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders characterised by the design or properties of the core
    • G21C1/024—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders characterised by the design or properties of the core where the core is divided in zones with fuel and zones with breeding material
    • 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
    • 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
    • G21C3/322—Means to influence the coolant flow through or around the 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
    • G21C3/326—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
    • 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)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
GB4404273A 1972-10-06 1973-09-19 Nuclear reactor fuel elements Expired GB1431475A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE2249049A DE2249049C2 (de) 1972-10-06 1972-10-06 Reaktorkern für schnelle flüssigmetallgekühlte Leistungsreaktoren

Publications (1)

Publication Number Publication Date
GB1431475A true GB1431475A (en) 1976-04-07

Family

ID=5858328

Family Applications (1)

Application Number Title Priority Date Filing Date
GB4404273A Expired GB1431475A (en) 1972-10-06 1973-09-19 Nuclear reactor fuel elements

Country Status (6)

Country Link
JP (1) JPS4971393A (US20100056889A1-20100304-C00004.png)
BE (1) BE805453A (US20100056889A1-20100304-C00004.png)
DE (1) DE2249049C2 (US20100056889A1-20100304-C00004.png)
FR (1) FR2202337B1 (US20100056889A1-20100304-C00004.png)
GB (1) GB1431475A (US20100056889A1-20100304-C00004.png)
IT (1) IT995566B (US20100056889A1-20100304-C00004.png)

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1276225B (de) * 1961-07-07 1968-08-29 Siemens Ag Brennelement fuer fluessigkeits- bzw. gasgekuehlte Atomreaktoren
FR1519594A (fr) * 1966-12-05 1968-04-05 Commissariat Energie Atomique Assemblage combustible pour réacteur nucléaire
DE1564219A1 (de) * 1966-12-22 1970-02-19 Interatom Brennelement fuer gas- oder fluessigkeitsgekuehlte Kernreaktoren
BE703561A (US20100056889A1-20100304-C00004.png) * 1967-09-07 1968-03-07
DE2010927C3 (de) * 1970-03-07 1980-02-14 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Brennelement fur einen Kernreaktor mit hohem und schnellem Neutronenfluß x
FR2115003B1 (US20100056889A1-20100304-C00004.png) * 1970-11-20 1973-11-30 Commissariat Energie Atomique

Also Published As

Publication number Publication date
FR2202337B1 (US20100056889A1-20100304-C00004.png) 1978-07-13
FR2202337A1 (US20100056889A1-20100304-C00004.png) 1974-05-03
IT995566B (it) 1975-11-20
BE805453A (fr) 1974-01-16
DE2249049A1 (de) 1974-04-18
JPS4971393A (US20100056889A1-20100304-C00004.png) 1974-07-10
DE2249049C2 (de) 1984-04-19

Similar Documents

Publication Publication Date Title
ES418350A1 (es) Perfeccionamientos introducidos en un nucleo de reactor nu- clear refrigerado por liquido.
GB915190A (en) Improvements in nuclear reactors
GB1389174A (en) Nuclear reactor
GB1169714A (en) Nuclear Reactor Fuel Elements
GB1245757A (en) Improvements in or relating to nuclear reactors
GB915338A (en) A core for a thermal nuclear reactor
GB1431475A (en) Nuclear reactor fuel elements
ES428493A1 (es) Perfeccionamientos en reactores de agua a presion.
GB1285464A (en) Improvements in or relating to nuclear reactors
IT1090883B (it) Dispositivo di misura del flusso neutronico per reattori nucleari
ES448407A2 (es) Perfeccionamientos en estructuras de casilleros para aloja- miento de elementos combustibles de reactores nucleares.
GB1169868A (en) Nuclear Fuel Assembly
GB914351A (en) Improvements in or relating to fuel elements
GB1241441A (en) Improvements in or relating to nuclear reactors
ES331160A1 (es) Un gran reactor nuclear rapido.
GB1292559A (en) A handling system comprising two rotary plugs for a nuclear reactor
CH451336A (de) Atomkraftwerk mit einem gasgekühlten Reaktor und einer Gasturbinen-Kraftanlage
LIPPINCOTT Measurement of the temperature dependence of k sub infinity for a(U-233) O 2-thO HTGR lattice(Temperature dependence measurement of k sub infinity for(U-233) O 2-ThO 2 lattice for design and safety analysis of advanced high temperature gas cooled reactors)
Little Jr et al. NUCLEAR PARAMETERS AND PARAMETRIC STUDIES FOR THE FAST TEST REACTOR (FTR).
GB989393A (en) Improvements in or relating to nuclear reactor fuel elements
BE762216A (fr) Four pour la desagregation thermique et chimique d'elements combustibles pour reacteurs nucleaires
Höchel Structural changes in briefly treated uranium dioxide with and without neutron irradiation as an aid in determining temperature distribution in fuel elements for nuclear reactors(Structural changes in briefly treated uranium dioxide with and without neutron irradiation as aid in determining temperature distribution in fuel elements for nuclear reactors)
BOZZI Measurement of the distribution of specific output in some mock-ups irradiated in the RITMO reactor(Specific power distribution of uranium oxide and uranium oxide boron oxide mixture fuel rods in RITMO nuclear reactor)
CH526836A (de) Brennstoffstab für gasgekühlte Hochtemperatur-Kernreaktoren sowie Verwendung desselben
SE381943B (sv) Anordning vid kernreaktor for instellning och uppberning av brenslestavar

Legal Events

Date Code Title Description
PS Patent sealed [section 19, patents act 1949]
PCNP Patent ceased through non-payment of renewal fee