BE630217A - - Google Patents

Info

Publication number
BE630217A
BE630217A BE630217DA BE630217A BE 630217 A BE630217 A BE 630217A BE 630217D A BE630217D A BE 630217DA BE 630217 A BE630217 A BE 630217A
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 BE630217A publication Critical patent/BE630217A/xx

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/06Casings; Jackets
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/04Thermal reactors ; Epithermal reactors
    • G21C1/06Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08Heterogeneous 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
    • G21C1/10Heterogeneous 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
    • G21C1/12Heterogeneous 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
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/04Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material
    • G21C15/06Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material in fuel elements
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/02Devices or arrangements for monitoring coolant or moderator
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/02Devices or arrangements for monitoring coolant or moderator
    • G21C17/028Devices or arrangements for monitoring coolant or moderator for monitoring gaseous coolants
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/041Means for removal of gases from fuel elements
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/16Details of the construction within the casing
    • G21C3/18Internal spacers or other non-active material within the casing, e.g. compensating for expansion of fuel rods or for compensating excess reactivity
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42Selection of substances for use as reactor fuel
    • G21C3/58Solid reactor fuel Pellets made of fissile material
    • G21C3/62Ceramic fuel
    • G21C3/64Ceramic dispersion fuel, e.g. cermet
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C5/00Moderator or core structure; Selection of materials for use as moderator
    • G21C5/12Moderator or core structure; Selection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C5/00Moderator or core structure; Selection of materials for use as moderator
    • G21C5/12Moderator or core structure; Selection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
    • G21C5/126Carbonic moderators
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Ceramic Engineering (AREA)
  • Dispersion Chemistry (AREA)
  • Organic Low-Molecular-Weight Compounds And Preparation Thereof (AREA)
  • Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
  • Treatment Of Liquids With Adsorbents In General (AREA)
BE630217D 1962-03-28 BE630217A (US20110232667A1-20110929-C00004.png)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB11842/62A GB954718A (en) 1962-03-28 1962-03-28 Improvements in or relating to high temperature gas cooled reactors

Publications (1)

Publication Number Publication Date
BE630217A true BE630217A (US20110232667A1-20110929-C00004.png) 1900-01-01

Family

ID=9993694

Family Applications (1)

Application Number Title Priority Date Filing Date
BE630217D BE630217A (US20110232667A1-20110929-C00004.png) 1962-03-28

Country Status (7)

Country Link
US (1) US3275522A (US20110232667A1-20110929-C00004.png)
AT (1) AT248560B (US20110232667A1-20110929-C00004.png)
BE (1) BE630217A (US20110232667A1-20110929-C00004.png)
CH (1) CH406458A (US20110232667A1-20110929-C00004.png)
GB (2) GB954718A (US20110232667A1-20110929-C00004.png)
LU (1) LU43434A1 (US20110232667A1-20110929-C00004.png)
NL (1) NL290809A (US20110232667A1-20110929-C00004.png)

Families Citing this family (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1446411A (fr) * 1965-06-09 1966-07-22 Commissariat Energie Atomique Procédé d'inhibition de la corrosion du graphite dans un réacteur nucléaire
US3356585A (en) * 1967-05-08 1967-12-05 Edwin L Zebroski Vented fuel system
US3519537A (en) * 1968-02-02 1970-07-07 Westinghouse Electric Corp Internal gas adsorption means for nuclear fuel element
GB1438525A (en) * 1973-08-21 1976-06-09 Central Electr Generat Board Gas cooled nuclear reactors
US4189348A (en) * 1976-07-26 1980-02-19 General Atomic Company Fuel rod assembly to manifold attachment
FR2513797A1 (fr) * 1981-09-30 1983-04-01 Commissariat Energie Atomique Dispositif de protection neutronique superieure pour assemblage de reacteur nucleaire
US4596690A (en) * 1983-12-21 1986-06-24 The United States Of America As Represented By The United States Department Of Energy Fission gas release restrictor for breached fuel rod
DE3641993A1 (de) * 1986-12-09 1988-06-23 Kernforschungsanlage Juelich Hochtemperaturreaktor
US4842812A (en) * 1987-09-11 1989-06-27 Westinghouse Electric Corp. Reactor coolant crud control by particulate scavenging and filtration
CN101800464B (zh) * 2010-01-28 2011-11-09 清华大学 高温气冷堆氦气空间的密封传动装置及其驱动装置

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
BE562864A (US20110232667A1-20110929-C00004.png) * 1956-11-30
BE581473A (US20110232667A1-20110929-C00004.png) * 1958-08-08
US3141829A (en) * 1960-04-19 1964-07-21 Fortescue Peter Fuel element

Also Published As

Publication number Publication date
LU43434A1 (US20110232667A1-20110929-C00004.png) 1963-05-27
AT248560B (de) 1966-08-10
US3275522A (en) 1966-09-27
NL290809A (US20110232667A1-20110929-C00004.png) 1900-01-01
GB1013102A (en) 1965-12-15
GB954718A (en) 1964-04-08
CH406458A (de) 1966-01-31

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