CH370169A - Channel for fuel material elements of a nuclear reactor and method of manufacturing this channel - Google Patents

Channel for fuel material elements of a nuclear reactor and method of manufacturing this channel

Info

Publication number
CH370169A
CH370169A CH446760A CH446760A CH370169A CH 370169 A CH370169 A CH 370169A CH 446760 A CH446760 A CH 446760A CH 446760 A CH446760 A CH 446760A CH 370169 A CH370169 A CH 370169A
Authority
CH
Switzerland
Prior art keywords
channel
manufacturing
nuclear reactor
fuel material
material elements
Prior art date
Application number
CH446760A
Other languages
French (fr)
Inventor
Alfille Lucien
Original Assignee
Commissariat Energie Atomique
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 Commissariat Energie Atomique filed Critical Commissariat Energie Atomique
Publication of CH370169A publication Critical patent/CH370169A/en

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
    • 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
    • G21C15/20—Partitions or thermal insulation between fuel channel and moderator
    • 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
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/06—Casings; Jackets
    • G21C3/12—Means forming part of the element for locating it within the reactor core
    • 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

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
  • Organic Low-Molecular-Weight Compounds And Preparation Thereof (AREA)
CH446760A 1959-04-29 1960-04-21 Channel for fuel material elements of a nuclear reactor and method of manufacturing this channel CH370169A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR793521A FR1233087A (en) 1959-04-29 1959-04-29 New use of vitreous silica

Publications (1)

Publication Number Publication Date
CH370169A true CH370169A (en) 1963-06-30

Family

ID=8714292

Family Applications (1)

Application Number Title Priority Date Filing Date
CH446760A CH370169A (en) 1959-04-29 1960-04-21 Channel for fuel material elements of a nuclear reactor and method of manufacturing this channel

Country Status (7)

Country Link
BE (1) BE589760A (en)
CH (1) CH370169A (en)
DE (1) DE1238113B (en)
FR (1) FR1233087A (en)
GB (1) GB941668A (en)
LU (1) LU38532A1 (en)
NL (1) NL250968A (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
NL277876A (en) * 1961-05-02 1900-01-01
FR1387264A (en) * 1963-12-18 1965-01-29 Commissariat Energie Atomique nuclear reactor fuel element

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
NL103807C (en) * 1955-07-27
DE1010660B (en) * 1956-04-19 1957-06-19 Siemens Ag Protective sleeve for fissile material elements of nuclear reactors
DE1031901B (en) * 1957-01-26 1958-06-12 Siemens Ag Gas-cooled nuclear reactor

Also Published As

Publication number Publication date
DE1238113B (en) 1967-04-06
GB941668A (en) 1963-11-13
LU38532A1 (en)
FR1233087A (en) 1960-10-12
NL250968A (en)
BE589760A (en) 1960-08-01

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