FR1323725A - Improvements to fuel elements - Google Patents

Improvements to fuel elements

Info

Publication number
FR1323725A
FR1323725A FR889736A FR889736A FR1323725A FR 1323725 A FR1323725 A FR 1323725A FR 889736 A FR889736 A FR 889736A FR 889736 A FR889736 A FR 889736A FR 1323725 A FR1323725 A FR 1323725A
Authority
FR
France
Prior art keywords
fuel elements
fuel
elements
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
FR889736A
Other languages
French (fr)
Inventor
Gauthron Marc Salesse Maurice
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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
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
Priority to BE628975D priority Critical patent/BE628975A/xx
Application filed by Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Priority to FR889736A priority patent/FR1323725A/en
Priority to LU43245D priority patent/LU43245A1/xx
Priority to DEC29251A priority patent/DE1242300B/en
Priority to GB8072/63A priority patent/GB970687A/en
Application granted granted Critical
Publication of FR1323725A publication Critical patent/FR1323725A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • G21C3/28—Fuel elements with fissile or breeder material in solid form within a non-active casing
    • 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
    • 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
    • G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
    • 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
    • G21C3/16—Details of the construction within the casing
    • G21C3/20—Details of the construction within the casing with coating on fuel or on inside of casing; with non-active interlayer between casing and active material with multiple casings or multiple active layers
    • 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
    • G21C3/38—Fuel units consisting of a single fuel element in a supporting sleeve or in another supporting element
    • 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)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Metallurgy (AREA)
  • Laminated Bodies (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)
FR889736A 1962-03-02 1962-03-02 Improvements to fuel elements Expired FR1323725A (en)

Priority Applications (5)

Application Number Priority Date Filing Date Title
BE628975D BE628975A (en) 1962-03-02
FR889736A FR1323725A (en) 1962-03-02 1962-03-02 Improvements to fuel elements
LU43245D LU43245A1 (en) 1962-03-02 1963-02-22
DEC29251A DE1242300B (en) 1962-03-02 1963-02-26 Uranium carbide based nuclear reactor fuel element
GB8072/63A GB970687A (en) 1962-03-02 1963-02-28 Improvements in fuel elements for nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR889736A FR1323725A (en) 1962-03-02 1962-03-02 Improvements to fuel elements

Publications (1)

Publication Number Publication Date
FR1323725A true FR1323725A (en) 1963-04-12

Family

ID=8773860

Family Applications (1)

Application Number Title Priority Date Filing Date
FR889736A Expired FR1323725A (en) 1962-03-02 1962-03-02 Improvements to fuel elements

Country Status (5)

Country Link
BE (1) BE628975A (en)
DE (1) DE1242300B (en)
FR (1) FR1323725A (en)
GB (1) GB970687A (en)
LU (1) LU43245A1 (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5626248A (en) * 1995-04-17 1997-05-06 Talus Corporation Therapeutic hand-held drinking apparatus
DE102005030231B4 (en) 2005-06-29 2007-05-31 Forschungszentrum Karlsruhe Gmbh Method for applying a high-temperature suitable FeCrAl protective layer, cladding tube with such a protective layer applied and use of such a cladding tube

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1037606B (en) * 1957-08-29 1958-08-28 Degussa Clad sleeve for nuclear reactor fuel elements
BE571786A (en) * 1957-10-16

Also Published As

Publication number Publication date
GB970687A (en) 1964-09-23
BE628975A (en)
LU43245A1 (en) 1963-04-22
DE1242300B (en) 1967-06-15

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