LU43434A1 - - Google Patents

Info

Publication number
LU43434A1
LU43434A1 LU43434DA LU43434A1 LU 43434 A1 LU43434 A1 LU 43434A1 LU 43434D A LU43434D A LU 43434DA LU 43434 A1 LU43434 A1 LU 43434A1
Authority
LU
Luxembourg
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.)
Filing date
Publication date
Application filed filed Critical
Publication of LU43434A1 publication Critical patent/LU43434A1/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)
  • Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
  • Organic Low-Molecular-Weight Compounds And Preparation Thereof (AREA)
  • Treatment Of Liquids With Adsorbents In General (AREA)
LU43434D 1962-03-28 1963-03-27 LU43434A1 (xx)

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
LU43434A1 true LU43434A1 (xx) 1963-05-27

Family

ID=9993694

Family Applications (1)

Application Number Title Priority Date Filing Date
LU43434D LU43434A1 (xx) 1962-03-28 1963-03-27

Country Status (7)

Country Link
US (1) US3275522A (xx)
AT (1) AT248560B (xx)
BE (1) BE630217A (xx)
CH (1) CH406458A (xx)
GB (2) GB1013102A (xx)
LU (1) LU43434A1 (xx)
NL (1) NL290809A (xx)

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 (xx) * 1956-11-30
BE581473A (xx) * 1958-08-08
US3141829A (en) * 1960-04-19 1964-07-21 Fortescue Peter Fuel element

Also Published As

Publication number Publication date
GB1013102A (en) 1965-12-15
GB954718A (en) 1964-04-08
US3275522A (en) 1966-09-27
BE630217A (xx) 1900-01-01
CH406458A (de) 1966-01-31
NL290809A (xx) 1900-01-01
AT248560B (de) 1966-08-10

Similar Documents

Publication Publication Date Title
BE616548R (xx)
BE629845A (xx)
BE629975A (xx)
BE380301A (xx)
BE489310A (xx)
BE538252A (xx)
BE538831A (xx)
BE541929A (xx)
BE553896A (xx)
BE559145A (xx)
BE586180A (xx)
BE592434A (xx)
BE599783A (xx)
BE604335A (xx)
BE608197A (xx)
BE609543A (xx)
BE612190A (xx)
BE612311A (xx)
BE612464A (xx)
BE612847A (xx)
BE612926A (xx)
BE613108A (xx)
BE613190A (xx)
BE613298A (xx)
BE613319A (xx)