FR1480109A - nuclear fuel element and process for its manufacture - Google Patents

nuclear fuel element and process for its manufacture

Info

Publication number
FR1480109A
FR1480109A FR974911A FR974911A FR1480109A FR 1480109 A FR1480109 A FR 1480109A FR 974911 A FR974911 A FR 974911A FR 974911 A FR974911 A FR 974911A FR 1480109 A FR1480109 A FR 1480109A
Authority
FR
France
Prior art keywords
manufacture
nuclear fuel
fuel element
nuclear
fuel
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
FR974911A
Other languages
French (fr)
Inventor
David E Goslee
Louis Frank
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.)
US Atomic Energy Commission (AEC)
Original Assignee
US Atomic Energy Commission (AEC)
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 claimed from US283126A external-priority patent/US3318695A/en
Application filed by US Atomic Energy Commission (AEC) filed Critical US Atomic Energy Commission (AEC)
Priority to FR974911A priority Critical patent/FR1480109A/en
Application granted granted Critical
Publication of FR1480109A publication Critical patent/FR1480109A/en
Expired legal-status Critical Current

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
    • G21C3/42Selection of substances for use as reactor fuel
    • G21C3/58Solid reactor fuel Pellets made of fissile material
    • G21C3/62Ceramic fuel
    • G21C3/626Coated fuel particles
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C21/00Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
    • G21C21/02Manufacture of fuel elements or breeder elements contained in non-active casings
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C21/00Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
    • G21C21/02Manufacture of fuel elements or breeder elements contained in non-active casings
    • G21C21/12Manufacture of fuel elements or breeder elements contained in non-active casings by hydrostatic or thermo-pneumatic canning in general by pressing without lengthening, e.g. explosive coating
    • 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
    • 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)
  • Manufacturing & Machinery (AREA)
  • Dispersion Chemistry (AREA)
FR974911A 1963-05-24 1964-05-19 nuclear fuel element and process for its manufacture Expired FR1480109A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
FR974911A FR1480109A (en) 1963-05-24 1964-05-19 nuclear fuel element and process for its manufacture

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US283126A US3318695A (en) 1963-05-24 1963-05-24 Method of producing nuclear fuel elements of stainless steel coated uo particles
FR974911A FR1480109A (en) 1963-05-24 1964-05-19 nuclear fuel element and process for its manufacture

Publications (1)

Publication Number Publication Date
FR1480109A true FR1480109A (en) 1967-05-12

Family

ID=26207711

Family Applications (1)

Application Number Title Priority Date Filing Date
FR974911A Expired FR1480109A (en) 1963-05-24 1964-05-19 nuclear fuel element and process for its manufacture

Country Status (1)

Country Link
FR (1) FR1480109A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2954849A1 (en) * 2009-12-31 2011-07-01 Commissariat Energie Atomique PROCESS FOR PRODUCING A CERMET COMPRISING URANIUM DIOXIDE PARTICLES
CN115132378A (en) * 2022-07-08 2022-09-30 中国核动力研究设计院 ODS (oxide dispersion strengthened) stainless steel-based dispersion micro-packaging rod-shaped fuel element and reactor

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2954849A1 (en) * 2009-12-31 2011-07-01 Commissariat Energie Atomique PROCESS FOR PRODUCING A CERMET COMPRISING URANIUM DIOXIDE PARTICLES
WO2011080474A1 (en) * 2009-12-31 2011-07-07 Commissariat A L'energie Atomique Et Aux Energies Alternatives Method for producing a cermet comprising uranium dioxide particles
CN115132378A (en) * 2022-07-08 2022-09-30 中国核动力研究设计院 ODS (oxide dispersion strengthened) stainless steel-based dispersion micro-packaging rod-shaped fuel element and reactor

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